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Organized by

In association with

Indian Nuclear Society

Water and Steam Chemistry Division, BARCDAE Advisory Committee on Steam and Water Chemistry (COSWAC)

Supported byIndian Society for Radiation and Photochemical Science (ISRAPS)Board of Research in Nuclear Sciences (BRNS)Atomic Energy Regulatory Board (AERB)Nuclear Power Corporation of India Limited (NPCIL)Association of Environmental Analytical Chemistry of India (AEACI)

Book of Abstracts

Symposium on Water

Chemistry and Corrosion

in Nuclear Power Plants in

Asia - 2015

Convention Centre, Anupuram, India

02 - 04 September, 2015

Asian Water Chemistry

Symposium Series

AWC 2015

PCM

Typewriter

PCM

Typewriter

Foreword

We are happy to host the Asian Water Chemistry Conference entitled ‘Symposium on

Water Chemistry and Corrosion in Nuclear Power Plants in Asia-2015’ (AWC-2015) during

September 02-04, 2015 at the Convention Centre Anupuram, Kalpakkam (Tamil Nadu). This is

the first ever Asian Water Chemistry Conference being organized in India. The symposium is

organized jointly by the Indian Nuclear Society (INS), Committee on Steam & Water Chemistry

(COSWAC) of the Department of Atomic Energy (DAE) and the Water & Steam Chemistry

Division (WSCD) of Bhabha Atomic Research Centre (BARC). DAE has attached critical

importance to R&D in water chemistry and corrosion, and WSCD in close association with

COSWAC is contributing to the high standards of water chemistry in Indian nuclear reactors in

accordance with plant safety and regulatory requirements. The organizers of AWC-2015 are

thankful to the Core Committee for giving them the responsibility of organizing this event in India,

thereby providing the Indian researchers, nuclear plant chemists and operators an opportunity to

showcase their R&D work and plant experience.

AWC-2015 has received an overwhelming response from R&D institutes and utilities of

India, Japan, South Korea, Taiwan, China and Germany. Indian participation is drawn from

BARC, Nuclear Power Corporation of India, Atomic Energy Regulatory Board, Bharatiya

Nabhikiya Vidyut Nigam, Indira Gandhi Centre for Atomic Research, Heavy Water Board,

Institute of Plasma Research, Raja Ramanna Centre for Advance Technology, M/s Larson &

Toubro, M/s Adani Infra India Ltd, and a few academic institutes. Over 150 delegates including

20 from overseas are expected to participate in the symposium.

AWC-2015 will have 3 plenary talks, 7 invited talks, 23 technical talks and over 50 poster

presentations covering topics of concern to PWR, BWR, PHWR, AHWR and VVER. The abstracts

of these talks/presentations are compiled in this volume and they cover a wide spectrum of issues

such as primary system operating experience, chemistry of boiling water reactor and other

advanced reactor, corrosion of plant materials, decontamination and dose reduction, basic research

in water chemistry steam cycle performance and process water, and issues relating to condenser

cooling water. We are confident that AWC-2015 will provide a useful platform for deliberations

on recent advances and thus focusing in the challenges and opportunities in the area of water

chemistry and corrosion.

We gratefully acknowledge the valuable advice of the Advisory Committee and the

dedicated work of the members of the Symposium Organizing Committee and Local

Organizing Committee. We extend our warm welcome to all the delegates from India and

abroad, and wish them memorable and intellectually satisfying stay over three days of the

symposium.

Dr. B.N. Jagatap Chairman, Organizing Committee

On behalf of the Organizing and Local Organizing Committees

National Advisory committee

Chairman

Dr. R. K. Sinha, Secretary, DAE

Members

Shri. S. S. Bajaj, Chairman, AERB, Mumbai

Shri. Sekhar Basu, Director, BARC, Mumbai

Dr. P. R. Vasudeva Rao, Director, IGCAR, Kalpakkam

Dr. P. Chellapandi, CMD, BHAVINI, Kalpakkam

Dr. Vijayamohanan K. Pillai, Director, CECRI, Karaikudi

Shri. T. J. Koteeswaran, Station Director, MAPS, Kalpakkam

Dr. M. A. Atmanand, Director, NIOT, Chennai

Dr. B. N. Jagatap, Director, Chemistry Group, BARC, Mumbai

Dr. K. L. Ramakumar, Director, Isotope Group, BARC, Mumbai

Dr. P. K. Vijayan, Director, RDDG, BARC, Mumbai

Dr. J. K. Chakravartty, Director, Materials Group, BARC, Mumbai

Shri. N. Nagaich, ED (CP&CC), NPCIL

Shri Ravindranath, ED (LWR), NPCIL

Shri U.C. Muktibodh, ED (Engg), NPCIL

Dr. T. Jayakumar, Director, MMG, IGCAR, Kalpakkam

Shri. Amitava Roy, Facility Director, BARC-F, Kalpakkam

Dr. Usha Natesan, Director, Centre for Research, Anna University, Chennai

Dr. J. B. Joshi, Homi Bhabha Chair, HBNI, Mumbai

Shri. S. A. Bharadwaj, President, Indian Nuclear Society, Mumbai

Dr. S. K. Apte, HBNI, Mumbai

Dr. R. K. Singh, Secretary, Indian Nuclear Society, Mumbai

Core Committee Representatives

Prof. Yosuke Katsumura, Tokyo University, Japan

Prof. Xinqiang Wu, Key Laboratory of Institute of Metal Research, Chinese Academy of Sciences, China

Prof. Tsung Kuang Yeh, National Tsing Hua University, Taiwan

Prof. In Hyoung Rhee, Soonchunhyang University, South Korea

National Organizing committee

Dr. B. N. Jagatap, BARC, Chairman

Dr. S. Velmurugan, WSCD, Convener

Dr. S. K. Aggarwal, Retd. AD, RC&I group, BARC

Dr. C. M. Das, BRNS, BARC

Dr. S. Dutta, BARC

Dr. K. Hari Krishna, MAPS, NPCIL

Shri. Y. V. Harinath, WSCD, BARC-F (Treasurer)

Smt. S. Jayashree, RED, BARC

Dr. U. Kamachi Mudali, IGCAR

Shri. T. V. Krishna Mohan, WSCD, BARC-F

Shri. Mahendra Prasad, AERB

Dr. P. K. Mathur, Retd. Head, WSCL

Dr. D. B. Naik, RPCD, BARC

Dr. S. V. Narasimhan, Retd. AD, CG, BARC

Prof. E. Natarajan, Anna University

Dr. D. K. Palit, ISRAPS, BARC

Dr. B. S. Panigrahi, FBTR, IGCAR

Prof. V. S. Raja, IIT-Mumbai

Shri. A. K. Rajput, RAPS#7&8, NPCIL

Shri. R. Ramakrishnan, PRPD, BARCF

Dr. S. Rangarajan, WSCD, BARC-F

Dr. A. L. Rufus, WSCD, BARC-F

Shri. R. R. Sahaya, NPCIL

Dr. B. Sengupta, NPCIL

Dr. R. S. Sharma, ROMG, BARC

Dr. B. Venkatraman, INS, Kalpakkam Branch

Dr. V. P. Venugopalan, WSCD, BARC-F

Dr. G. K. Vithal, HWB

Dr. Vivekanand Kain, MSD, BARC

Symposium organisers would like to thank the following organisations

for supporting the Symposium on Water Chemistry and Corrosion in

Nuclear Power Plants in Asia, 2015

September 2 (Day-1)

Symposium on Water Chemistry and Corrosion in Nuclear Power Plants

in Asia–2015, Convention Centre, Anupuram, India

Opening Ceremony 09:30 – 10:00

Inauguration Plenary Session 10:00 – 11:05

Plenary Lecture 1 10:00 – 10:30

Prof. Yosuke Katsumura, JRIA, Japan, AWC-102, “Current Situation of Nuclear Power in Japan after

Fukushima Nuclear Accident”

Plenary Lecture 2 10:30 – 11:00

Shri. U. C. Muktibodh, NPCIL, India, AWC-160 “Chemistry and Corrosion Issues in Indian Nuclear

Power Plants”

Summing up 11:00 – 11:05

Coffee Break/Photo Session 11:05 – 11:20

Session-1 Primary System Operating Experience (PWRs/PHWRs/VVERs) 11: 20– 12:30

Invited Talk 1 11:20 – 11:45

Dr. S. V. Narasimhan, BARC (Retd.), India, AWC-167 “Chemistry Management in Indian Nuclear

Reactors”

Technical Talk 1 11:45 – 12:05

Shri. P. Selvavinayagam, NPCIL, India, AWC-118 “Water Chemistry Experiences with VVER’s at

Kudankulam”


Dr. Hee-Sang Shim, KAERI , S. Korea, AWC-150 “Prediction Method of Sub-Cooled Nucleate

Boiling on the Nuclear Fuel Cladding in Primary Water

Condition Using Acoustic Emission Technique”

Summing up 12:25 – 12:30

Lunch Break 12:30 – 13:30

Session-2 Boiling Water Reactor / Advanced Reactor Experience 13:30 – 15:00

Invited Talk 2 13:30 – 13:55

Smt. Jayasree Sriram, BARC, India, AWC-157 “Water Chemistry Features of Advanced Heavy

Water Reactor”

Technical Talk 3 13:55– 14:15

Dr. Kenji Hisamune, JAPC, Japan, AWC-101 “Approach to Mitigate Intergranular Stress

Corrosion Cracking and Dose Rate Reduction by Water

Chemistry Control in Tokai-2”


Dr. Deepa Papachan, NPCIL, India AWC-133, “Fuel Performance Review at Taps 1&2 With

Respect to Reactor Coolant Crud & Alpha Activity”


Dr. Subrata Bera, AERB, India. AWC-185, “Iodine Chemistry and Associated Interaction

Under Severe Accident Conditions” Summing up 14:55 – 15:00

Coffee Break 15:00 – 15:15

Session-3 Corrosion of Plant Materials 15:15 – 17:05

Invited Talk 3 15:15 – 15:40

Dr. Vivekanand Kain, BARC, India AWC-169, “Correlating Size of Scallops to Single Phase Flow

Accelerated Corrosion in Nuclear Power Plants”


Dr. Helmut Nopper, AREVA, Germany, AWC-148, “ FAC Surveillance Concept with the Predictive

Code COMSY”


Prof. Yutaka Watanabe, Tohoku Univ., Japan, AWC-128, “Benchmark Study of Prediction Models for Pipe

Wall Wastage”


Shri. Mahendra Prasad, AERB, India, AWC-112, “ Mass Transfer Coefficient Enhancement Factor

in Pipe Bend – 3 Dimensional Analysis”


Dr. Yasuhiro Chimi, JAEA, Japan, AWC-113, “Water Radiolysis Effect on IASCC Growth

Behavior in BWR Water Conditions in Highly Irradiated

Austenitic Stainless Steel”

Summing up 17:00 – 17:05

Poster Session 17:05 – 19:00

Cultural Program 19:00 - 20:00

Convention Centre, Anupuram

Dinner 20:00 - 21:30

End of first day

September 3 (Day-2)

Session-4 Decontamination and Dose Reduction 09:00 – 10:10

Invited Talk 4 09:00 – 09:25

Dr. S. Velmurugan, BARC, India, AWC-166 “Dose Reduction and Decontamination in Indian

Nuclear Power Plant”


Shri. Osamu Shibasaki, Toshiba Corporation,

Japan, AWC-115 “Co-60 Deposition on Carbon-Steel

Structural Materials after Seawater Infiltration in BWR

Plant”

Technical Talk 11 09:45 - 10:05

Shri V. S. Sathyaseelan, BARC, India, AWC-162, “High Temperature Decontamination of Stainless

Steel Surfaces”

Summing up 10:05 – 10:10


Session-5 Basic Research 10:25 – 11:35

Invited Talk 5 10:25 – 10:50

Prof. Xinqiang Wu, IMR, China, AWC-100 "Development Status of Nuclear Power in China

and Some Fundamental Research Progress on PWR Primary

Water Chemistry in China"


Dr. Puspalatha Rajesh, BARC, India, AWC-161, “Effect of High Concentration Gadolinium

Nitrate in Reactor Moderator System”


Dr. P. Chandramohan, BARC, India, AWC-136, “Cation Distribution in Ferrites and its Effects on

The Chemical Dissolution Behaviour”

Summing up 11:30 – 11:35

Session-6 Steam Cycle Performance and Process Water Systems 11:35-13:05

Invited Talk 6 11:35 – 12:00

Dr. Christoph Michael Stiepani, AREVA,

Germany, AWC-130,“AREVA’s Toolbox for Long-Term

Best Performance and Reliable Operation of Nuclear Steam

Generators”


Dr. K. Ganapathy Subramanian, IGCAR, India, AWC -140, “Two Decades of Experience with Steam-Water

Chemistry Maintenance of Fast Breeder Test Reactor”


Dr. P. K. Pal, NPCIL, India, AWC-105, “Identification of Boiler Tube Leak in RAPS-2

by Measuring Iodine-134 Activity in Boiler Water Sample of

RAPS Using Gamma Spectrometric Techniques.”


Dr. Meng Jen Chen, Taiwan power company

Taiwan, AWC-170, “Improve Steam Generator Moisture

Carryover Rate at Maanshan NPS by Cleaning Steam Drum

Internal Sludge ”

Summing up 13:00 – 13:05

Lunch Break 13:05 – 14:00

Session-7 Condenser Cooling Water Issues 14:00 – 15:30

Invited Talk 7 14:00 – 14:25

Dr. V. P. Venugopalan, BARC, India, AWC-147, “Biofouling Control in Power Plant Cooling

Water Systems: Challenges and Prospects”


Dr.Vinita Vishwakarma, Sathyabama

University, India, AWC-149, “Nanophase Modified Fly

Ash Concrete with Superior Concrete Properties, Durability

and Biofouling Resistance for Seawater Applications ”


Dr. B. Anandkumar, IGCAR, India, AWC-151 “Control of Biofouling on Titanium Condenser

Tubes with The Use of Electroless Copper Plating”


Shri. A. K. Mohanty, IGCAR, India AWC-155 “Biofouling Community Pattern on Various

Metallic Surfaces in The Coastal Waters of Kalpakkam,

Southwestern Bay of Bengal ”

Summing up 15:25 – 15:30


Session-8 Future Trends and New Developments 15:45 – 16:55

Invited Talk 8 15:45 – 16:10

Dr. Alphonsa Joseph, IPR, India, AWC-109 “Plasma Nitrocarburizing Process –A Solution to

Improve Wear and Corrosion Resistance”


Dr. B. Anupkumar, BARC, India, AWC-173 “Metal Ion Imprinted Polymers for Effective

Radioactive Waste Segregation in Nuclear Industry”


Shri. Jaymin Gandhi, Adani Infra India Ltd.,

India, AWC-121, “Environmental Sustainability by

Adoption of Alternate Cooling Media for Condenser

Cooling”

Summing up 16:50 – 16:55


Feedback Session 17:10 – 18:00

Dinner 19:00-21:00 NPCIL Guest House, Kalpakkam

End of Second day

September 4 (Day-3)

Technical Visit 9:30:12:00 Visit to Madras Atomic Power Station and NDDP,

Kalpakkam

Lunch 13:00 :14:00 Convention Centre, Anupuram

End of Technical program

Visit to ‘DakshinaChitra’ 14:00:18:00

‘DakshinaChitra’ is an exciting cross cultural living museum

of art, architecture, lifestyles, crafts and performing arts

of South India. (www.dakshinachitra.net)

S. No. UID Title and Authors P.No

Plenary Session

1 AWC-102

CURRENT SITUATION OF NUCLEAR POWER IN JAPAN AFTER

FUKUSHIMA NUCLEAR ACCIDENT

Yosuke Katsumura

1

2 AWC100

DEVELOPMENT STATUS OF NUCLEAR POWER IN CHINA AND

FUNDAMENTAL RESEARCH PROGRESS ON PWR PRIMARY WATER

CHEMISTRY IN CHINA

Xinqiang Wu, Xiahe Liu, En-Hou Han, Wei Ke, and Yuming Xu

2

3 AWC-160 INDIAN NUCLEAR POWER PRORAMME AND EXPERIENCE IN

WATER CHEMISTRY AND CORROSION

U.C Mukthibodh -

Session –I

1 AWC-167 CHEMISTRY MANAGEMENT IN INDIAN NUCLEAR REACTORS

S.V. Narasimhan 3

2 AWC-118 WATER CHEMISTRY EXPERIENCES WITH VVERs AT

KUDANKULAM

D. Rout, T.C. Upadhyay, Ravindranath, P. Selvinayagam and R.S. Sundar 4

3 AWC-150

PREDICTION METHOD OF SUB-COOLED NUCLEATE BOILING ON

THE NUCLEAR FUEL CLADDING IN PRIMARY WATER CONDITION

USING ACOUSTIC EMISSION TECHNIQUE

Hee-Sang Shim, Seung-Heon Baek, Kaige Wu, Deok Hyun Lee and Do Haeng

Hur

5

Session -II

1 AWC-157 WATER CHEMISTRY FEATURES OF ADVANCED HEAVY WATER

REACTOR

Jayasree Sriram, Vivekanad Kain, S.Velmurugan and K.Vijayan 6

2 AWC-101

APPROACH TO MITIGATE INTERGRANULAR STRESS CORROSION

CRACKING AND DOSE RATE REDUCTION BY WATER CHEMISTRY

CONTROL IN TOKAI-2

Kenji Hisamune

7

3 AWC-133 FUEL PERFORMANCE REVIEW AT TAPS 1&2 WITH RESPECT TO

REACTOR COOLANT CRUD & ALPHA ACTIVITY

Deepa Papachan, A.K.Panda and S.M.Maskey 8

4 AWC-185

IODINE CHEMISTRY AND ASSOCIATED INTERACTION UNDER

SEVERE ACCIDENT CONDITIONS

Dhanesh B. Nagrale, Subrata Bera, Anuj Kumar Deo, U. K. Paul, M. Prasad and

A. J. Gaikwad

9


Session –III

1 AWC-169

CORRELATING SIZE OF SCALLOPS TO SINGLE PHASE FLOW

ACCELEARATED CORROSION IN NUCLEAR POWER PLANTS

Vivekanand Kain, V. Dubey, S. Roychowdhury, M. Kiran Kumar and D.

K.Barua

10

2 AWC-148 FAC SURVEILLANCE CONCEPT WITH THE PREDICTIVE CODE

COMSY

Helmut Nopper and Andre Zander 11

3 AWC-128 BENCHMARK STUDY OF PREDICTION MODELS FOR PIPE WALL

WASTAGE

Yutaka Watanabe 12

4 AWC-112

MASS TRANSFER COEFFICIENT ENHANCEMENT FACTOR IN PIPE

BEND – 3 DIMENSIONAL ANALYSIS

Mahendra Prasad, P Madasamy, T V Krishnamohan, S Velumurugan,

Arunkumar Sridharan and Avinash J. Gaikwad

13

5 AWC-113

WATER RADIOLYSIS EFFECT ON IASCC GROWTH BEHAVIOR IN

BWR WATER CONDITIONS IN HIGHLY IRRADIATED AUSTENITIC

STAINLESS STEEL

Yasuhiro Chimi, Shigeki Kasahara, Kuniki Hata, Yutaka Nishiyama, Hitoshi

Seto, Kazuhiro Chatani, Yuji Kitsunai and Masato Koshiishi

14

Session –IV

1 AWC-166 DEVELOPMENT OF METHODS TO CONTROL RADIATION FIELD

AND CORROSION IN PHWRS

S.Velmurugan 15

2 AWC-114

DEVELOPMENT OF A METHOD TO LOWER RECONTAMINATION

AFTER CHEMICAL DECONTAMINATION BY DEPOSITING Pt

NANO PARTICLES

Tsuyoshi Ito, Hideyuki Hosokawa, Toshimasa Ohashi, Makoto Nagase,Mizuho

Tsuyuki, Nobuyuki Ota and Motohiro Aizawa

16

3 AWC-115

Co-60 DEPOSITION ON CARBON-STEEL STRUCTURAL

MATERIALS AFTER SEAWATER INFILTRATION IN BWR PLANT

Hiromitsu Inagaki, Osamu Shibasaki, Koji Negishi, Yumi Yaita, Masato

Okamura, Yutaka Uruma, Seiji Yamamoto and Hajime Hirasawa

17

4 AWC-162

HIGH TEMPERATURE DECONTAMINATION OF STAINLESS STEEL

SURFACES

V. S. Sathyaseelan, A. L. Rufus, P. Chandramohan, H. Subramanian and S.

Velmurugan

18

Session –V

1 AWC-161 EFFECT OF HIGH CONCENTRATION GADOLINIUM NITRATE IN

REACTOR MODERATOR SYSTEM

Debasis Mal, Puspalata Rajesh, S. Rangarajan and S. Velmurugan 19

2 AWC-173 METAL ION IMPRINTED POLYMERS FOR EFFECTIVE

RADIOACTIVE WASTE SEGREGATION IN NUCLEAR INDUSTRY

B. Anupkumar 20

3 AWC-136 CATION DISTRIBUTION IN FERRITES AND ITS EFFECTS ON THE

CHEMICAL DISSOLUTION BEHAVIOUR

P.Chandramohan, M.P.Srinivasan and S.Velmurugan 21


Session -VI

1 AWC-130 AREVA’s TOOLBOX FOR LONG-TERM BEST PERFORMANCE AND

RELIABLE OPERATION OF NUCLEAR STEAM GENERATORS

Andreas Drexler, Steffen Weiss, Neil Caris and Christoph Stiepani 22

2 AWC-140 TWO DECADES OF EXPERIENCE WITH STEAM-WATER CHEMISTRY

MAINTENANCE OF FAST BREEDER TEST REACTOR

K. Ganapathy Subramanian, A. Suriyanarayanan and B. S. Panigrahi 23

3 AWC-105

IDENTIFICATION OF BOILER TUBE LEAK IN RAPS-2 BY MEASURING

IODINE-134 ACTIVITY IN BOILER WATER SAMPLE OF RAPS USING OF

GAMMA SPECTROMETRIC TECHNIQUES.

P. K. Pal and R. C. Bohra

24

4 AWC-170 IMPROVE STEAM GENERATOR MOISTURE CARRYOVER RATE AT

MAANSHAN NPS BY CLEANING STEAM DRUM INTERNAL SLUDGE

Meng-Jen Chen 25

Session -VII

1 AWC-147 BIOFOULING CONTROL IN POWER PLANT COOLING WATER

SYSTEMS: CHALLENGES AND PROSPECTS

V.P.Venugopalan 26

2 AWC-149

NANOPHASE MODIFIED FLY ASH CONCRETE WITH SUPERIOR

CONCRETE PROPERTIES, DURABILITY AND BIOFOULING

RESISTANCE FOR SEAWATER APPLICATIONS

Vinita Vishwakarma, R.P. George U. Sudha, D. Ramachandran, Kalpana Kumari, R.

Preetha, U.Kamachi Mudali and C. S. Pillai

27

3 AWC-151 CONTROL OF BIOFOULING ON TITANIUM CONDENSER TUBES WITH

THE USE OF ELECTROLESS COPPER PLATING

B. Anandkumar, R.P. George, D. Ramachandran and U. Kamachi Mudali 28

4 AWC-155

BIOFOULING COMMUNITY PATTERN ON VARIOUS METALLIC

SURFACES IN THE COASTAL WATERS OF KALPAKKAM,

SOUTHWESTERN BAY OF BENGAL

Gouri Sahu, K.K. Satpathy, A.K.Mohanty and V.K.Bindu

29

Session –VIII

1 AWC-109 PLASMA NITROCARBURIZING PROCESS –A SOLUTION TO IMPROVE

WEAR AND CORROSION RESISTANCE

Alphonsa Joseph, Ghanshyam Jhala and S. Mukherjee 30

2 AWC-154 FEASIBILITY STUDY OF A NON-CHEMICAL TECHNIQUE FOR

FOULING CONTROL

Yaw-Ming Chen 31

3 AWC-121 ENVIRONMENTAL SUSTAINABILITY BY ADOPTION OF ALTERNATE

COOLING MEDIA FOR CONDENSER COOLING Jaymin Gandhi and Nilesh Patel

32

S. No. UID Title and Authors P. No

Poster Session

1 AWC-103

RADIOLYSIS OF WATER AT HIGH TEMPERATURE AND PRESSURE

CONDITIONS: A PICOSECOND PULSE RADIOLYSIS EXPERIMENT

AND NUMERICAL SIMULATIONS

Yusa Muroya, Tetsuro Yoshida, Yosuke Katsumura, Shinichi Yamashita,

Mingzhang Lin and Takahiro Kozawa

33

2 AWC-104

INJECTION OF NANO-PARTICLES IN MITIGATING FLOW

ACCELERATED CORROSION(FAC) DAMAGE IN THE SECONDARY

SYSTEM OF NUCLEAR POWER PLANTS(NPPS)

Dong Seok Lim, Hee Kwon Ku and Jae Seon Cho

34

3 AWC-106

ADDITION OF OXYGEN IN THE INLET OF RECOMBINER UNIT IN

MODERATOR COVER GAS SYSTEM TO FACILITATE

RECOMBINATION OF DEUTERIUM AND OXYGEN TO BRING

DEUTERIUM CONCENTRATION IN SAFE LIMITS

P. K. Pal and S. Mukherjee

35

4 AWC-107

DETERMINATION OF MOISTURE CONTENT IN STEAMS BY

ANALYZING SODIUM CONTENT IN STEAM GENERATOR WATER &

STEAMS CONDENSATE OF A NUCLEAR POWER PLANT USING ION

CHROMATOGRAPHIC TECHNIQUE AT DIFFERENT LEVELS OF

BOILER WATER

P.K.Pal and R.C.Bohra

36

5 AWC-108 EXPERIENCE ON KKNPP VVER 1000 MWe WATER CHEMISTRY

S. Ganesh, S. Selvaraj, M.R. Balasubramanian, P. Selvavinayagam#, Suresh Kumar

Pillai, 37

6 AWC-110 KINETICS OF DISSOLUTION OF Ni-Cr CONTAINING IRON OXIDES

SERIES (NICRXFE2-XO4) IN HMnO4 MEDIUM

V. Balaji, P. Chandramohan, Ashish Tiwari, S. Rangarajan and S. Velmurugan 38

7 AWC-111 MEASUREMENT OF HENRY’S LAW CONSTANT IN HYDROGENATED

LIOH/H3BO3 SOLUTION

E. H. Lee, G. G. Lee, D. H. Lee, and D. H. Hur 39

8 AWC-116

SEASONAL VARIATION IN TRIHALOMETHANE LEVELS AT

KALPAKKAM AND IN RELATION TO ORGANIC CARBON

PRECURSORS

R. Rajamohan, V. P. Venugopalan and Usha Natesan

40

9 AWC-117

ROLE OF REDUCTANTS IN CONTROL OF CORROSION OF

MATERIALS RELATED TO NUCLEAR REACTORS

Padma S.Kumar, Sinu Chandran, Puspalata Rajesh, D.Mohan, S.Rangarajan and

S.Velmurugan

41

10 AWC-119

IMPROVEMENT IN PERFORMANCE OF DM PLANT, SECONDARY

SYSTEMS FOR ACHIEVING CHEMISTRY PERFORMANCE INDICATOR

OF KGS-3&4

B.S.Sahu, P.G.Raichur, M Srinivas and M P Hansora

42

11 AWC-120 EXPERIENCE OF CHEMICAL TREATMENT FOR CONTROLLING

CORROSION IN IDCT WATER OF KGS 3&4.

V.Uday Kumar and B.S.Sahu 43

12 AWC-122 ELECTROCHEMICAL PASSIVATION STUDIES OF ZIRCALOY IN

PRESENCE OF METAL ION

Sinu Chandran, H. Subramanian, N. Sreevidya, S. Rangarajan and S. Velmurugan 44


Poster Session

13 AWC-123

A COMPARATIVE STUDY OF THE CORROSION BEHAVIOUR OF

GRADE 91 AND RAFM STEELS AT AMBIENT TEMPERATURE

N Sreevidya, Sinu Chandran, C.R. Das, S. K Albert, S Rangarajan and S

Velmurugan

45

14 AWC-124 PERFORMANCE RESTORATION TECHNIQUE DEVELOPED FOR

FOULED HEAT EXCHANGER

Dipankar Nanda, Babloo Tiwari and R. M. Pandey 46

15 AWC-125 NITROGEN COMPOUNDS FORMATION IN N2-WATER AND N2-

MOISTURE SYSTEMS

G.R. Dey and T.N. Das 47

16 AWC-126 EVALUATION OF ALUMINUM BRASS COUPONS IN BWR CONDENSATE

ENVIRONMENT IN PRESENCE OF METAL

K K Bairwa, V S Tripathi, A Kumar and D B NaiK 48

17 AWC-127 SYNTHESIS AND CHARACTERIZATION OF V(HCOO)2•2H2O

V S Tripathi K K Bairwa1, S N Achary and D B. NaiK 49

18 AWC-129 STUDIES ON FAILURE ANALYSIS OF STAINLESS STEEL ION

EXCHANGE HOPPER AT NAPS

S.K.Upadhyay, Ranjana Kusari, and Brij Mohan 50

19 AWC-131

ANTIMONY (Sb) SORPTION AT HIGH TEMPERATURE AND PRESSURE

ON ZIRCALOY, CARBON STEEL (CS) AND MAGNETITE COATED CS

(MCS) SURFACES

S. J. Keny, B. K. Gokhale, A. G. Kumbhar, Santanu Bera, Saibal Basu and S.

Velmurugan

51

20 AWC-132

EFFECT OF ANTIMONY(III) ON CARBON STEEL CORROSION

INHIBITION BY MOLYBDATE IN CITRIC ACID SOLUTION

Vinit K. Mittal, Y. Raghavendra, Santanu Bera, S. Sumathi, S. Rangarajan, S.V.

Narasimhan and S.Velmurugan

52

21 AWC-134 RADIOACTIVE LIQUID WASTE DISCHARGE REDUCTION STRATEGIES

AT TAPS 1&2

Deepa Papachan, A.K.Panda, S.M.Maskey, M.Joshi, and V.S.Daniel 53

22 AWC-135 EVALUATION OF ADVANCED HOT CONDITIONING PROCESS FOR

PHWRS

P.Chandramohan, M.P.Srinivasan and S.Velmurugan 54

23 AWC-137 TREATMENT OF FAST REACTOR LIQUID WASTE-

ELECTROCHEMICAL METHOD

Swapan Kumar Mahato, R. Sudha, P. Muralidaran and S. Anthonysamy 55

24 AWC-138 FIXATION OF NUCLEAR WASTE INTO GLASS MATRICES FOR

ULTIMATE DISPOSAL

G. Hazra, T Das and P. Mitra 56

25 AWC-139 ANTIMONY SORPTION PROPERTIES OF CHITOSAN – NANO TIO2

COMPOSITE BEADS

Padala Abdul Nishad, B. Anupkumar and S. Velmurugan 57

26 AWC-141

HEAVY METALS-BIOREMEDIATION BY HIGHLY RADIORESISTANT

DEINOCOCCUS RADIODURANS BIOFILM : PROSPECTIVE USE IN

NUCLEAR REACTOR DECONTAMINATION

Sudhir K. Shukla and T. Subba Rao

58

27 AWC-142 OPERATING CONDITIONS INFLUENCE CORROSION OF CARBON

STEEL IN A FRESHWATER DISTRIBUTION SYSTEM

T. Subba Rao 59


Poster Session

28 AWC-143 ISOLATION AND CHARACTERIZATION OF THE MICROBIAL

COMMUNITY OF A FRESHWATER DISTRIBUTION SYSTEM

P. Balamurugan and T. Subba Rao

60

29 AWC-144 MICROFOULING ASSESSMENT AND ITS CONTROL IN A HEAVY

WATER PRODUCTION UNIT

Rajesh Kumar and T. Subba Rao 61

30 AWC-145 CORROSION OF ALLOY D9 IN LIQUID SODIUM

R. Sudha, K. Chandran, P. Muralidaran and S. Anthonysamy 62

31 AWC-146 THREE DECADES OF EXPERIENCE WITH COOLING WATER

SYSTEM OF A FAST REACTOR

A.Suriyanarayanan and B.S.Panigrahi 63

32 AWC-156

WATER TREATMENT WITH CHLORINE: INFLUENCE OF SOURCE

WATER CHARACTERISTICS ON CHLORINATION & CBPS

FORMATION

R K Padhi, S Subramanian and K K Satpathy

64

33 AWC-158

ENTRAINMENT AND IMPINGEMENT OF AQUATIC FAUNA AT

COOLING WATER SYSTEM OF MADRAS ATOMIC POWER STATION

(MAPS)

S. Barath Kumar, N. P. I. Das and K.K. Satpathy

65

34 AWC-159 SURFACE AND ELECTROCHEMICAL CHARACTERIZATION OF

NANO ZINC FERRITE COATING ON CARBON STEEL

Sumathi Suresh, S. Rangarajan and S velmurugan 66

35 AWC-163 EVALUATION OF CORROSION INHIBITORS FOR HIGH

TEMPERATURE DECONTAMINATION APPLICATIONS

V. S. Sathyaseelan, A. L. Rufus and S. Velmurugan 67

36 AWC-171

DEVELOPMENT OF LEACHING METHOD FOR THE ANALYSIS OF

PALLADIUM CATALYST USED IN THE MODERATOR COVER GAS

CIRCUIT OF MAPS BY ICP-OES

S.Vijayalakshmi and S.Annapoorani

68

37 AWC-172 DISSOLUTION OF COBALT METAL POWDER V.S.Sathyaseelan, A.L.Rufus and S.Velmurugan

69

38 AWC-174

STUDIES WITH ANTI FOULING COATING ON SEAWATER INTAKE

SYSTEM SCREENS OF MAPS

N.Sankar, V.S.Santhanam, P.Umapathi, K.Hari Krishna, D.Rajendran,

P.S.Murthy and V.P. Venugopalan,

70

39 AWC-175

INFLUENCE OF GEOMETRY OF PIPE ON FLOW ACCELERATED

CORROSION - A STUDY UNDER NEUTRAL PH CONDITION

P.Madasamy, M.Mukunthan, P.Chandramohan, T.V.Krishna Mohan, and

S.Velmurugan

71

40 AWC-176

EVALUATION OF PLASMA COATED CARBON STEEL TO RESIST

FLOW ACCELERATED CORROSION

P.Madasamy, J. Alphonsaa,J. Ghanshyam, S. Mukherjee, M.Mukunthan,

P.Chandramohan, T.V.KrishnaMohan, ,E.Natarajan and S.Velmurugan

72

S. No. UID Title and Authors P. No

Poster Session

41 AWC-177 PREPARATION AND DISSOLUTION OF URANIUM DIBUTYL

PHOSPHATE (U-DBP)

M.K.Dhanesh, A.L.Rufus and S.Velmurugan 73

42 AWC-178 STUDIES ON GADOLINIUM PRECIPITATION IN MODERATOR

SYSTEM OF NUCLEAR REACTOR

Akhilesh C Joshi, Puspalata Rajesh, A.L.Rufus and S.Velmurugan 74

43 AWC-179

OBSERVATIONS ON THE REMOVAL OF GADOLINIUM FROM

THE MODERATOR SYSTEM OF PRESSURISED HEAVY WATER

REACTOR (PHWR) AND ADVANCED HEAVY WATER REACTOR

(AHWR)

V. Praveena, Padma S.Kumar, A.L.Rufus and S.Velmurugan

75

44 AWC-180

CHEMISTRY MANAGEMENT OF GENERATOR STATOR WATER

SYSTEM

N. Sankar, V.S. Santhanam, S.R. Ayyar, P. Umapathi, P. Jeena, K. Hari

Krishna, D.Rajendran

76

45 AWC-181

STUDIES WITH SOLID CHLORINE CHEMICAL FOR

CHLORINATION OF SEA WATER SYSTEMS

N.Sankar, P.Kumaraswamy, V.S.Santhanam, P.Jeena, K.Hari Krishna and

D.Rajendran,

77

46 AWC-182 CORROSION RATE OF CARBON STEEL IN NEUTRON SHIELD

TANK WATER

R.Ramakrishnan, N.Rathinasamy and K.V.Ravi 78

47 AWC-183 OPTIMUM THICKNESS EVALUATION OF ZrO2 COATING ON

TYPE 304L STAINLESS STEEL FOR CORROSION PROTECTION

Nidhi Garg, Santanu Bera, V. S. Tripathi, Vijay Karki and S. Velmurugan 79

48 AWC-184

IODINE REMOVAL IN CONTAINMENT FILTERED VENTING

SYSTEM DURING NUCLEAR ACCIDENT

SubrataBera, D. B. Nagrale, Anuj Kumar Deo, U. K. Paul, M. Prasad and A.

J. Gaikwad

80

49 AWC-186 AN OPERATIONAL EXPERIENCE WITH COOLING TOWER

WATER SYSTEM IN CHILLING PLANT

Manju B Rajan, Ankan Roy and KV Ravi 81

50 AWC-187

CONTAINMENT BEHAVIOR DURING MOLTEN CORIUM

CONCRETE INTERACTION

Anuj Kumar Deo, S. P. Lakshmanan, S. Bera, Balbir K. Singh, P. K.

Baburajan, R. S. Rao, U. K. Paul and A. J. Gaikwad

82

51 AWC-188

DEUTERISATION OF MIXED BED ION EXCHANGE RESIN:

KINETICS STUDY

Satinath Ghosh, M. K. Tripathy, Kajal Dhole, T. Vasudevan, Satyam Shukla

and R. S. Sharma

83

52 AWC-189

FEASIBILITY STUDY ON NANO-STRUCTURED COATINGS TO

MIGATE FLOW-ACCELERATED CORROSION OF CARBON

STEEL PIPING SYSTEM

Seunghyun Kim, Jeong Won Kim and Ji Hyun Kim

84

Symposium on water chemistry and corrosion in nuclear power plants in Asia-2015

1

AWC-102 CURRENT SITUATION OF NUCLEAR POWER IN JAPAN

AFTER FUKUSHIMA NUCLEAR ACCIDENT

Yosuke Katsumura

Japan Radioisotope Association

2-28-35 Honkomagome, Bunkyo-ku, Tokyo 113-8941 Japan

*Corresponding author: [email protected]

ABSTRACT

On March 11, 2011 we had the Great East Japan Earthquake and induced tsunami,

which attacked the Fukushima Daiichi Nuclear Power Station (NPS). After Fukushima Nuclear

Accident, not only all the power reactors but also all research reactors are out of service over

four years. At the beginning of August a power reactor, Sendai #1, Kyushu Electric Power

Company, restarted the operation for the first time and commercial operation will be approved

after the inspection of start-up at the end of August or the beginning of September.

In this talk, I would like to present briefly the situation of the NPS before and after Fukushima

Nuclear Accident, new regulatory requirements for LWR plants by the Nuclear Regulation

Authority, and current status and future of the Fukushima Daiichi NPS.

Keywords: Fukushima Daiichi Nuclear Accident, new requirements, Nuclear Regulatory

Authority, Decommissioning of Fukushima NPS


2

AWC-100 DEVELOPMENT STATUS OF NUCLEAR POWER IN CHINA AND

FUNDAMENTAL RESEARCH PROGRESS ON PWR PRIMARY WATER

CHEMISTRY IN CHINA

Xinqiang Wu 1*, Xiahe Liu 1, En-Hou Han 1, Wei Ke 1, Yuming Xu 2

1 Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for

Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research,

Chinese Academy of Sciences, Shenyang 110016, P.R. China

(* Tel: +86-24-23841883; Fax: +86-24-23894149; E-mail: [email protected]) 2 China nuclear energy association, 12 Chegongzhuang Street, Xicheng District, Beijing

100037, P.R. China


Abstract

China's non-fossil fuels are expected to reach 20% in primary energy ratio by 2030. It

is urgent for China to speed up the development of nuclear power to increase energy supply,

reduce gas emissions and optimize resource allocation. Chinese government slowed down

the approval of new nuclear power plant (NPP) projects after Fukushima accident in 2011. At

the end of 2012, the State Council approved the nuclear safety program and adjusted long-

term nuclear power development plan (2011-2020), the new NPPs’ projects have been

restarted. In June 2015, there are 23 operating units in mainland in China with total installed

capacity of about 21.386 GWe; another 26 units are under construction with total installed

capacity of 28.5 GWe. The main type of reactors in operation and under construction in China

is pressurized water reactor (PWR), including the first AP1000 NPPs in the world (units 1 in

Sanmen) and China self-developed Hualong one NPPs (units 5 and 6 in Fuqing). Currently,

China's nuclear power development is facing historic opportunities and also a series of

challenges. One of the most important is the safety and economy of nuclear power.

The optimization of primary water chemistry is one of the most effective ways to minimize

radiation field, mitigate material degradation and maintain fuel performance in PWR NPPs,

which is also a preferred path to achieve both safety and economy for operating NPPs. In

recent years, an increased attention has been paid to fundamental research and engineering

application of PWR primary water chemistry in China. The present talk mainly consists of four

parts: (1) development status of China's nuclear power industry; (2) safety of nuclear power

and operating water chemistry; (3) fundamental research progress on Zn-injected water

chemistry in China; (4) summary and future.

Keywords: China nuclear power, water chemistry, Zn-injection, fundamental research

mailto:[email protected]


3

AWC-167

CHEMISTRY MANAGEMENT IN INDIAN NUCLEAR REACTORS

S.V. Narasimhan

(ex) Chairman COSWAC, (Retd.) AD, CG, BARC


Abstract

Starting with a couple of BWR, the department of atomic energy in India established

PHWR based reactors of different capacities in quite a good number. Subsequently reactors

of different types like VVER (already operational in Kudankulam), PWRs, AHWR, PFBR are

being pursued vigorously to meet the energy demand and to comply with green power

requirement. From the beginning of nuclear power programme, monitoring, maintaining &

management of good chemistry domain in the cooling water circuits were practiced in a

dedicated manner through the formation of an advisory group which in turn advises the

national regulatory body on chemistry related issues. Enough care was taken to devise a

suitable management model to implement these programmes in a meticulous manner. Over

the years it has worked well not only in enabling the power plants to maintain water chemistry

domain within the allowed specification limits but also in implementing newer techniques and

procedures for enhancing operational safety and efficiency. The paper highlights some of

these aspects.


4

AWC-118

WATER CHEMISTRY EXPERIENCES WITH VVERS AT KUDANKULAM 1D Rout#, 1T.C. Upadhyay, 1Ravindranath, 2P. Selvinayagam & 2 R.S Sundar

1Directorate of Operations, NPCIL, Mumbai 2Kudankulam Nuclear Power Station, Kudankulam

#Corresponding author: [email protected]

Abstract

Kudankulam Nuclear Power Project-1&2 (KKNPP-1&2) are pressurised water cooled

VVERs of 1000 MW€ each. KKNPP-1 is presently on its first cycle of operation and KKNPP-2

is on the advanced stage of commissioning with the successful completion of Hot Functional

tests. Water Chemistry aspects during various phases of commissioning of KKNPP-1 such as

Hot Run, Boric acid flushing, initial fuel Loading (IFL) , First approach to Criticality (FAC) are

discussed. The main objectives of the use of controlled primary water chemistry programme

during the hot functional tests are reviewed. The importance of the relevant water chemistry

parameters were ensured to have the quality of the passive layer formed on the primary

coolant system surfaces.

The operational experiences during the 1st cycle of operation of primary water chemistry,

radioactivity transport and build-up are presented. The operational experience of some VVER

units in the field of the primary water chemistry, radioactivity transport and build-up are

presented as a comparison to VVER at KKNPP. The effects of the initial passivated layer

formed on metal surfaces during hot functional tests, activated corrosion products levels in the

primary coolant under controlled water chemistry regime and the contamination/ radiation

situation are discussed. This report also includes the water chemistry related issues of

secondary water systems.


5

AWC-150

PREDICTION METHOD OF SUB-COOLED NUCLEATE BOILING ON THE

NUCLEAR FUEL CLADDING IN PRIMARY WATER CONDITION USING

ACOUSTIC EMISSION TECHNIQUE

Hee-Sang Shim#, Seung-Heon Baek, Kaige Wu, Deok Hyun Lee, Do Haeng Hur

Division of Nuclear Materials Safety Research, Korea Atomic Energy Research Institute

(KAERI), Republic of Korea

#Corresponding Author:

[email protected]

Abstract

Axial offset anomaly (AOA), which is defined as a significant negative axial offset

deviation from the predicted nuclear design value, has important operational and economic

consequences. It is well known that AOA is caused by the incorporation of boron within

corrosion product (crud) deposits on the upper span of fuel assembly. Crud depositions are

accelerated when the sub-cooled nucleate boiling (SNB) occurs on the fuel cladding surface

in the primary coolant including sufficient corrosion products. Many researchers have widely

studied a boiling process via various methods such as high-speed video camera and

temperature measurement with thermocouples to understand the crud deposition mechanism

as well as SNB condition. The detection and monitoring of SNB in terms of non-destructive

evaluation is one of promising technique for analyzing the crud deposition mechanism and

AOA phenomenon. In this work, we provided a prediction method of SNB on fuel cladding

using acoustic emission (AE) technique in a simulated primary circuit along with a relationship

between crud deposition and boiling process.

Crud deposition tests were performed in a simulated primary coolant including Ni- and Fe-

EDTA of each 20 ppm at 325oC. The fuel cladding temperature was controlled using an

internal heater in a temperature range of 330oC to 400oC and the boiling process was

investigated using piezoelectric AE sensor coupled with fuel cladding surface. The transition

of boiling process and bubble dynamics were successfully distinguished by AE signals in a

primary coolant condition. In addition, the crud deposition depended on the boiling process in

its properties and amount. These results indicate that the in-situ AE technique can be a

suitable prediction method for SNB in the PWR reactor core.

Keywords: Fuel cladding, Sub-cooled nucleate boiling, Acoustic emission, Crud deposition



6

AWC-157

WATER CHEMISTRY FEATURES OF ADVANCED HEAVY WATER REACTOR

Jayasree Srirama#, Vivekanad kainb, S.Velmuruganc and K.Vijayana aReactor Engineering Division, BARC, Mumbai

bMaterials Science Division, BARC, Mumbai cWater and Steam Chemistry Division, BARCF, kalpakkam

#Corresponding Author: [email protected]

Abstract

Advanced Heavy Water Reactor (AHWR) being designed in India proposes to use

Plutonium and Thorium as fuel. The objective is to extract energy from the uranium-233

formed from Thorium. It is a heavy water moderated and light water cooled tube type boiling

water reactor. It is a natural circulation reactor. Thus, it has got several advanced passive

safety features built into the system. The various watercoolant systems are listed below.

i) Main Heat transport System

ii) Feed water system

iii) Condenser cooling system

iv) Process water system and safety systems

As it is a tube type reactor, the radiolysis control differs from the normal boiling water reactor. The coolant enters the bottom of the coolant channel, boiling takes place and then the entire steam water mixture exits the core through the long tail pipes and reaches the moisture separator. Thus, there is a need to devise methods to protect the tail pipes from oxidizing water chemistry condition. Similarly, the moderator heavy water coolant chemistry differs from that of moderator system chemistry of PHWR. The reactivity worth per ppm of gadolinium and boron are low in comparison to PHWR. As a result, much higher concentration of neutron poison has to be added for planned shutdown, start up and for actuating SDS#2. The addition of higher concentration of neutron poison result in higher radiolytic production of deuterium and oxygen. Their recombination back to heavy water has to take into account the higher production of these gases. This paper also discusses the chemistry features of safety systems of AHWR. In addition, the presentation will cover the chemistry monitoring methodology to be implemented in AHWR.


7

AWC-101

APPROACH TO MITIGATE INTERGRANULAR STRESS CORROSION

CRACKING AND DOSE RATE REDUCTION BY WATER CHEMISTRY CONTROL

IN TOKAI-2

Kenji Hisamune

The Japan Atomic Power Company

1-1, Kanda-Mitoshiro-Cho, Chiyoda-Ku, Tokyo


Abstract

At the Tokai Daini Power Station (hereinafter Tokai-2; BWR, 1,100MWe, commenced

commercial operation in November 1978), I carried out material replacement and stress

release to maintain the integrity of structure materials. And, I reduced sulfate ion concentration

by improvement of the regenerative method (such as the Advanced Resin Cleaning System;

ARCS) of the condensate demineralizer ion-exchange resin to mitigate intergranular stress

corrosion cracking (IGSCC) of boiling water reactor (BWR) materials. In addition, I

suppressed reactor water oxide concentration by Hydrogen Water Chemistry during operation

and start up to mitigate IGSCC.

On the other hand, I worked on reduction of feed water iron concentration as the plant

which I did not install a pre-filter in of condensate demineralizer for dose rate reduction. I

improved operational change of condensate demineralizer ion-exchange resin regeneration

and regenerative method (ARCS) for improvement of crud removal efficiency. In this report, I

describe the improvement effect the water chemistry control (such as reduce of reactor water

sulfate ion concentration, reactor water oxide concentration and feed water iron concentration)

that I applied in Tokai-2 until now. In addition, I report dose rate reduction effect by the zinc

injection that started an application recently. And, I introduce the ECP monitoring plan with

the OLNCTM of the application plan in future.


8

AWC-133

FUEL PERFORMANCE REVIEW AT TAPS1&2 WITH RESPECT TO REACTOR

COOLANT CRUD & ALPHA ACTIVITY

Deepa Papachan#, A.K.Panda, S.M.Maskey

Technical Services Section, Tarapur Atomic Power Station 1& 2


Abstract

Tarapur Atomic Power Station -1&2 (TAPS-1&2) consists of twin unit of Boiling Water

Reactors (BWR) in India. The reactors were commissioned during 1969-1970 and their

present rated capacity is 530MWth. Each reactor core has 284 fuel assemblies.Fuel

performance monitoring at TAPS1&2 is carried out throughout the fuel cycle by means of

reactor physics parameters and several radiochemistry parameters e.g. gross gamma activity

level of Iodine isotopes in reactor coolant, fission product noble gases(FPNG mainly Xe and

Kr isotopes) radioactivity and their composition and monitoring of Cesium, Technicium-

Molybdenum, Neptunium activity in reactor coolant. A comparative analysis of all these

parameters helps in identifying the contribution of tramp uranium towards fuel performance,

time of fuel failure occurrence and conjuring the extent of failed fuel growth etc. This feedback

with regard to fuel performance during the fuel cycle not only guides in taking precautionary

measures with respect to activites to be carried out at refueling floor during refueling outage,

but it also increases the confidence level in leaky fuel detection at the end of the fuel cycle

refueling outage by wet sipping method. Fuel Reliability Indicator(FRI) for BWR reactors, as

provided by WANO is based on only the FPNG gases and is calculated for each reactor to

monitor the industry trend at global level with respect to achieving high fuel integrity in spite of

the fact that BWR reactors are of different generations.

Along with the above mentioned fuel performance monitoring parameters and FRI,

another radiochemical parameter which not only gives trend of fuel performance but also the

clean up or filter system performance with respect to removal of failed fuel fragments or

corrosion products is alpha activity of reactor coolant and fuel pool water. This paper compares

the trend of primary coolant and fuel storage pool alpha activity with respect to the FRI trend

of each reactor with an undernote that FRI reporting remains to be on higher side in spite of

zero fuel failure owing to the insufficient deduction of tramp uranium factor from FRI

calculation.


9

AWC-185

IODINE CHEMISTRY AND ASSOCIATED INTERACTION UNDER SEVERE

ACCIDENT CONDITIONS

Dhanesh B. Nagrale#, Subrata Bera, Anuj Kumar Deo, U. K. Paul,

M. Prasad and A. J. Gaikwad

Nuclear Safety Analysis Division, Atomic Energy Regulatory Board

Niyamak Bhavan, Anushaktinagar, Mumbai-400094


Abstract

In a highly improbable severe accident wherein the core cooling is decapicitated or

insufficient could lead to fuel elements melting and fission product release beyond the plant

limits. Nuclear power plants are designed with engineering systems and associated

operational procedures that provide an in-depth defence against such accidents. A good

understanding of iodine behaviour is required for the analysis of severe accident

consequences because Iodine is a major contributor to the potential source term for release

to the environment. Iodine speciation along the transport path from fuel to cooler regions of

heat transport system and into containment should be evaluated using various appropriate

models which leads to prediction of volatile iodine mole fraction, cesium to iodine ratio etc.

The roles of other elements mainly molybdenum, tellurium, uranium and lithium are also

important.

Iodine released from fuel, iodine transport in primary coolant system, reaction with

control rods are important. The behaviour of iodine-bearing particles is governed by aerosol

physics, depletion mechanisms gravitational settling, diffusiophoresis and thermophoresis.

Sorption and desorption of Iodine occurring on containment surface is also of importance. The

presence of gaseous organic compounds, oxidizing compounds on iodine, reactions of

aerosol Iodine with boron and formation of cesium iodide which results in more volatile Iodine

release in containment are important aspects. Water radiolysis products due to presence of

dissolved impurities such as dissolved oxygen, nitrate/nitrite (NO3 /NO2 ) produced by air

radiolysis, trace metal ions such as Fe2+/Fe3+ dissolved from steel surfaces, chloride ions

coming from the pyrolysis/radiolysis of polyvinyl material from cables and organic impurities

(RH) from painted surfaces and polymers also important and all above mentioned

phenomenon should be considered while calculating iodine released inside and outside

containment. Other important aspects which needs attention are re-suspension from iodine

loaded surfaces, coupling of thermal-hydraulics with iodine chemistry, temperature, relative

humidity and steam condensation and its influence on the re-suspension rates, condensing

conditions, etc.

The released Iodine from containment is allowed to pass through containment filtration

venting system (CFVS). CFVS consists of venturi scrubber and a scrubber tank. The scrubber

tank which is dosed with NaOH, NaS2O3 where iodine will react with the chemicals and

converts into NaI and Na2SO4. This paper elaborates about all above mentioned present status

and issues with respect to iodine chemistry and its behaviour during accident.

Keywords: Iodine, Volatile Iodine, Impurities, Organic and non-organic Iodine


10

AWC-169

CORRELATING SIZE OF SCALLOPS TO SINGLE PHASE FLOW

ACCELEARATED CORROSION IN NUCLEAR POWER PLANTS

Vivekanand Kain, V. Dubey, S. Roychowdhury, M. Kiran Kumar and D. K. Barua1

Materials Science Division, Bhabha Atomic Research Centre, Mumbai 400085, India

Nuclear Power Corporation of India Ltd., Anushaktinagar, Mumbai 400094, India

#Corresponding author:

Abstract

A comprehensive thinning monitoring program is in place for all the components of

high energy portions of secondary cycle systems of Indian nuclear power plants since 2006.

This program is based on initially establishing a baseline thickness data by extensive

ultrasonic examination on the components and then periodic thickness measurements to

establish thinning and flow accelerated corrosion (FAC) rates. In this extensive thinning

monitoring program, it has been observed that in a few cases the thinning are not by FAC

degradation. This program has also identified components that are more prone to FAC and

exhibit much higher FAC rates. These components are the focus of implementation of FAC

thinning control measures e.g. change of material or change in piping layout/geometry to

reduce flow rate/turbulence hence FAC. The extensive thickness monitoring data collected

during FAC monitoring from various power plants provided an oppourtunity to correlate the

size of scallops with the single phase FAC thinning rates. The extensive database thus

developed indicates a broad trend. More specific measurements in different ranges of scallop

sizes and FAC rates would be added to have a comprehensive database. Thus this provides

an oppourtunity to establish FAC rate from the examination of the scallop pattern on the inner

surface of the FAC affected component. This would be a very promising approach to confirm

the FAC rate measured by ultrasonic examination. Specific case studies with emphasis on

scallop patterns developed on cases of components showing low and high FAC rates are

covered. A selective case would be highlighted to emphasise that factors other than FAC also

lead to thinning.


11

AWC-148

FAC SURVEILLANCE CONCEPT WITH THE PREDICTIVE CODE COMSY

Helmut Nopper*, Andre Zander

AREVA GmbH Paul Gossen Str. 100, D-91058, Erlangen, Germany

*Corresponding Author: [email protected]

Abstract

Flow-Accelerated Corrosion (FAC) has become a major safety issue for operators of

NPPs. Experience shows, that severe wall thinning may cause spontaneously occurring pipe

ruptures. It is therefore necessary to develop efficient surveillance concepts for wall thinning

of piping,

vessels and mechanical equipment. Wall tinning is typically caused by flow-induced

degradation mechanisms like FAC, liquid droplet impingement erosion (LDI) and cavitation

erosion (CE). Areas suffering from such wall thinning effects are difficult to locate, as these

degradation mechanisms occur only locally for steel components operated under specific

conditions of flow, water chemistry and temperatures.

The reliable identification of system areas sensitive to wall thinning calls for a

comprehensive plant-wide strategy, considering the possible superposition of different

degradation mechanisms. The COMSY software supports this activity by providing the

predictive capability to calculate degradation rates and the functionality to analyze the relevant

operating conditions. Water chemical conditions are analyzed in each system and sub-system

in respect to e.g. pH- values or oxygen concentrations and thermal hydraulic operation

conditions are characterized for typical load cases experienced during plant service. Based on

these evaluations a degradation potential can be quantified using predictive models. Based on

these evaluations the inspection program can be optimized by focusing activities on

degradation sensitive areas.

An integrated inspection data management function ensures information feedback

from inspection activities. Inspection data is systematically evaluated and used to further

optimize service life predictions over the life cycle of the component.

This strategy is designed to provide a comprehensive, long-term surveillance of the

integrity of mechanical components. The computerized monitoring and lifetime surveillance

system provided by AREVA makes it possible to keep a lifetime consumption record as a basis

for safe operation and efficient maintenance and repair strategies.



12

AWC-128

BENCHMARK STUDY OF PREDICTION MODELS FOR PIPE WALL WASTAGE

Yutaka Watanabe

Tohoku University

Aoba-ku, Sendai, Miyagi 980-8579, Japan


Abstract

The research committee for studying pipe-wall-thinning management was established

in The Japan Society of Mechanical Engineers (JSEM) in Year 2008. Since then, the research

committee has been gathering and investigating technical information on flow induced pipe

wall wastage. As one of the core activities of the pipe-wall-thinning research committee,

“working group for prediction methods” has been set up and prediction models of pipe-wall

thinning have been reviewed in terms of their characteristics in prediction and required

specification to be used in pipe-wall-thinning management. A few prediction models of flow-

accelerated corrosion (FAC) and liquid droplet impingement erosion (LDI) have been reviewed

by comparing the predictions to experimental data and plant inspection data. This paper

describes the procedures and result status of the benchmark examinations.


13

AWC-112

MASS TRANSFER COEFFICIENT ENHANCEMENT FACTOR IN PIPE BEND – 3

DIMENSIONAL ANALYSIS

Mahendra Prasad1*, P Madasamy2, T V Krishnamohan 2, S Velumurugan2, Arunkumar

Sridharan3, Avinash J.Gaikwad1 1Atomic Energy Regulatory Board, Mumbai, India

2 WSCD, BARCF, Kalpakkam, India 3 IIT Bombay, Mumbai, India


Abstract

Flow Accelerated Corrosion (FAC) has plagued the power industry since long time.

The high velocity fluid at elevated temperatures is used for process requirements which

causes FAC in straight pipes exhibiting non-uniform corrosion and this is enhanced for junction

such as bends, orifices etc. Mass transfer coefficient (MTC) changes from its base value in

straight pipe (with same fluid parameters) for flow in bends, orifiec etc due to gross disturbance

of the velocity profile. Since MTC is related to wall thinning, its relative increase or decrease

is important to estimate for spatial degradation prediction. In this paper, computational fluid

dynamics (CFD) simulations are carried for 58o bend angle and 2D bend radius circular pipe

in three dimensions. Turbulent model K-ω with shear stress transport is found to perform well

for domain with geometric changes and this was the model for simulation. Since mass tranfer

boundary layer (MTBL) thickness δmtbl is related to the Schmidt number (Sc) and hydrodynamic

boundary layer thicknessd δh, as δmtbl ~ δh/(Sc1/3), MTBL is significantly smaller than δh and

hence boundary layer meshing was carried out deep into δmtbl. The simulation is related to an

experiment carried out for 58o bend angle and 2D bend radius circular carbon steel pipe

carrying water at 120oC under neutral pH conditions to determine the wall thinning at few

extrados locations. Uniform velocity was applied at the inlet. The flow velocity was 5 m/s at

room temperature. The ratio of the mass transfer coefficient at such locations to the straight

pipe coefficient (MTCR) is determined through simulation. As seen in literature, since the

dependence of MTCR on Re and Sc is not as strong as compared to pipe bend angle and

bend radius, CFD simulation at lower temperature is sufficient to get approximate MTC in

bends. The MTC increased in the extrados of the bend towards the outlet.

Key Words: Flow Accelerated Corrosion, Mass Transfer Coefficient, Turbulent Flow, Mass Transfer Boundary Layer


14

AWC-113

WATER RADIOLYSIS EFFECT ON IASCC GROWTH BEHAVIOR IN BWR

WATER CONDITIONS IN HIGHLY IRRADIATED AUSTENITIC STAINLESS

STEEL

Yasuhiro Chimi1,#, Shigeki Kasahara1, Kuniki Hata1, Yutaka Nishiyama1,

Hitoshi Seto2, Kazuhiro Chatani2, Yuji Kitsunai2, Masato Koshiishi2 1Japan Atomic Energy Agency (JAEA),

2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, JAPAN 2Nippon Nuclear Fuel Development,

2163 Narita-cho, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki 311-1313, JAPAN


Abstract

For study of water radiolysis effect caused by gamma-rays from radioactive material

on irradiation-assisted stress corrosion cracking (IASCC) growth behavior, crack growth tests

in highly irradiated austenitic stainless steel are performed in simulated BWR water conditions

(at ~563 K). The compact tension (CT) specimens made of 316L stainless steels are irradiated

with neutrons up to ~12 dpa in the Japan Materials Testing Reactor (JMTR). Post-irradiation

annealing at 973 K for 1 hour is applied to one of the specimens, which shows the recovery of

material properties corresponding to the unirradiated ones but the radioactivity of highly

irradiated material as it is. The gamma-ray absorbed dose rate in water is calculated near the

crack tip of the CT specimen, and the stable concentrations of H2O2, O2 and H2 in water near

the crack tip are estimated by radiolysis calculation for some feedwater conditions of normal

water chemistry (NWC), deaerated water and hydrogen water chemistry (HWC). The

preliminary results of the crack growth rate (CGR) for the highly irradiated specimens and the

annealed specimen are presented, and the relationship between the CGRs and the water

chemistry such as the concentrations of radiolytic species and the electrochemical corrosion

potential (ECP) is discussed.


15

AWC-166

DEVELOPMENT OF METHODS TO CONTROL RADIATION FIELD AND

CORROSION IN PHWRS

S.Velmurugan

Water and Steam Chemistry Division, BARC Facilities, Kalpakkam – 603 102

Tamilnadu, INDIA

Corresponding author: [email protected]

Abstract

Pressurized Heavy Water Reactors (PHWRs) is the mainstay of Indian Nuclear Power

Program. There are 18 PHWRs (220 MWe & 540 MWe) in operation and 4X700 MWe PHWRs

are under construction. In these reactors, as far as radiation field is concerned, the philosophy

of ALARA (As Low As Reasonably Achievable) is followed. The primary coolant system

chemistry control is given due consideration during operation so that corrosion of structural

material is minimized which in turn controls the radiation field. Development and application

of full system Dilute Chemical Decontamination(DCD) process helped to reduce the radiation

field in MAPS#1&2, RAPS#1&2, NAPS#1&2 and KAPS#1. PHWR being a tube type reactor,

it enables application of full system decontamination to its heavy water primary coolant

system. Significant reduction in radiation field and consequent savings in MANREM could be

achieved. Attempts are being made to understand the problem created by the release of

antimony activities (122Sb and 124Sb) during chemical decontamination and during planned

shutdown.

Passivation as a method to control the radiation field and corrosion is being studied.

Magnesium ion as a passivator to the ferrite filmed structural materials of PHWRs is being

investigated. In addition, as PHWRs uses carbon steel as structural material, the use of

passivation as a method to control flow accelerated corrosion (FAC) is also being studied.

Magnesium ion gets incorporated in the ferrite film formed over carbon steel structural material

and is expected to reduce the solubility of magnetite film thereby the FAC of feeders in

PHWRs.



16

AWC-114

DEVELOPMENT OF A METHOD TO LOWER RECONTAMINATION AFTER

CHEMICAL DECONTAMINATION BY DEPOSITING PT NANO PARTICLES

Tsuyoshi Ito1, Hideyuki Hosokawa1, Toshimasa Ohashi1, Makoto Nagase2,

Mizuho Tsuyuki2, Nobuyuki Ota2, Motohiro Aizawa2

1 Center for Technology Innovation-Energy, Research & Development Group, Hitachi Ltd., 7-

2-1 Omika-cho, Hitachi-shi, Ibaraki 319-1221 Japan 2 Hitachi Works, Hitachi-GE Nuclear Energy, Ltd., 3-1-1 Saiwai-cho, Hitachi-shi, Ibaraki 317-

0073 Japan


Abstract

Chemical decontamination is an effective method to reduce occupational radiation

exposure in boiling water reactors (BWRs) when carrying out such large-scale tasks as

overhauling primary recirculation pumps. In the chemical decontamination, oxides formed on

the surface of the stainless steel (SS) piping that incorporate the 60Co are dissolved with

reductive and oxidative chemical reagents. The SS base metal of the piping is exposed to

reactor water after the chemical decontamination and the growth rate of the oxide film that

incorporates the 60Co of the piping during plant operation just after the decontamination is

higher than that just before it. Therefore, there is a possibility that the deposition amount of 60Co on the piping just after decontamination is higher than that just before the chemical

decontamination. Actually, rapid deposition amount increases of 60Co within a few operating

cycles have been observed in some nuclear power plants. Then, we developed the Pt coating

(Pt-C) to lower the recontamination by 60Co after the chemical decontamination. In the Pt-C

process, a Pt layer is formed in an aqueous solution on the SS base metal of the piping using

sodium hexahydroxyplatinate (IV) and hydrazine.

In this study, we confirmed that the suppression effect by the Pt-C toward 60Co

deposition on SS using a 60Co deposition test under hydrogen water chemistry. The deposition

amounts of 60Co which were incorporated in oxides after 1000 h with and without Pt-C process

were about 90 and 10.2 Bq/cm2, respectively. The amount of 60Co deposition with Pt-C is

about 10% that of non-coated specimens.



17

AWC-115

Co-60 DEPOSITION ON CARBON-STEEL STRUCTURAL MATERIALS AFTER

SEAWATER INFILTRATION IN BWR PLANT

Hiromitsu Inagaki1, Osamu Shibasaki2#, Koji Negishi2, Yumi Yaita2,

sato Okamura2, Yutaka Uruma2, Seiji Yamamoto2, Hajime Hirasawa3 1Chubu Electric Power Co., Inc., 5561, Sakura, Omaezaki, Shizuoka, 437-1695, Japan

2Toshiba Corporation, 4-1, Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862, Japan 3Toshiba Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama 235-8523, Japan


Abstract

Seawater infiltration occurred during shutdown of the Hamaoka Unit 5 (H-5). Chloride

ion (Cl-) is known to affect the corrosion behavior of carbon steel, and it may change the

properties of the oxide film formed on the surface. Co-60 deposition in high-temperature water

is strongly related to the oxide film properties, and any change in the properties may affect the

Co-60 deposition after the plant is restarted. This paper shows the results of Co-60 deposition

tests of carbon steels under simulated H-5 water conditions. Specimens for the Co-60

deposition tests were prepared in three steps, which simulated the conditions of normal plant

operation, seawater infiltration, and chemical decontamination after the infiltration. The first

step was a prefilming step under Normal Water Condition (NWC). The second step included

two different conditions: seawater infiltration and keeping after infiltration. Prefilmed

specimens were immersed in 450 ppm Cl- diluted artificial seawater at 513 K for 24 hours.

Following that, the specimens were immersed in 50 ppm Cl- diluted artificial seawater at 323

K for 100–500 hours. During the second step, the prefilming oxide (NiFe2O4) flaked off in spots.

In the third step, the oxide remaining on some specimens after the second step was removed

chemically. The three types of prepared specimens, that is, a prefilmed specimen, an exposed

specimen, and an oxide-removed specimen, were used for the Co-60 deposition tests using

0.015 Bq/cm3 Co-60 solution for 500 or 1000 hours under NWC conditions. After the deposition

tests, the Co-60 activity was measured with a Ge detector. From the results of the deposition

test, at the spots where flaking occurred in the second step, only loose hematite was formed,

and generation of a new protective film was not observed. The amount of Co-60 deposited on

the exposed specimen was more than that on the prefilmed and oxide-removed specimens.

The simulated infiltrating conditions inhibited the regeneration of a protective film and caused

an increase in the amount of Co-60 deposited.

Keywords: Co-60, RI deposition, Seawater infiltration, Carbon steel, Chloride ion



18

AWC-162

STUDY ON THE DECONTAMINATION OF 400 SERIES STAINLESS STEEL

SURFACES AND DISSOLUTION OF CHROMIUM SUBSTITUTED NICKEL

FERRITES

V. S. Sathyaseelan, A. L. Rufus, P. Chandramohan, H. Subramanian and

S. Velmurugan#

Water and Steam Chemistry Division, Bhabha Atomic Research Centre Facilities,

Kalpakkam, Tamilnadu – 603 102, INDIA

#Corresponding email: [email protected]

Abstract

Full system decontamination of Primary Heat Transport system (PHT) of Pressurised

Heavy Water Reactors (PHWRs) is carried out using weak organic acids at about 90 °C.

During this low temperature process, decontamination factors (DFs) achieved on carbon steel

(CS) surface was quite good as it was effective in dissolving magnetite formed on CS surfaces.

However, the DF achieved on stainless steel (SS) and other non- CS surfaces were not that

appreciable as the process was not effective in dissolving Cr and Ni substituted oxides present

on these surfaces. “End fittings” surface was one such area where low DF was achieved. SS-

403 and SS-410 are the material of construction of “End Fittings” and “End Fitting Liners”

respectively. Hence, to develop an effective decontamination process for “End Fittings”

material surfaces, studies were carried out with SS-403 and SS-410 specimens. Passivated

SS-403 and SS-410 surfaces were prepared by exposing the specimens under simulated

PHWR PHT system chemistry conditions. The oxide film was characterised by chemical and

physical techniques such as XRD, Raman spectroscopy and SEM-EDX. Three formulations

evaluated for the dissolution of the oxide films formed over these alloys were i) Two-step

process consisting of oxidation and reduction reactions, ii) Dilute Chemical Decontamination

(DCD) and iii) high temperature Process at 160 °C. Material compatibility study also was

carried out in these three formulations. The two-step and high temperature processes could

dissolve the oxide film completely. But, the DCD process could remove only 60%. The two-

step process is time consuming and generates large quantity of waste. Whereas, the high

temperature process is less time consuming and generates only low volume of waste. Hence,

high temperature process is recommended for SS decontamination.

The high temperature process was evaluated for the dissolution of Cr substituted Ni ferrites

also. This type of oxides is formed over SS-300 series alloys. Ni substituted Cr ferrites of

composition NiCr(1-x)Fe(2-x)O4 (x = 0, 0.2, 0.4, 0.6, 0.8 and 1) were prepared by combustion

route, characterised by XRD and Raman spectroscopy. Dissolution study of these oxide

powders was carried out in NTA formulation at 160 °C. The formulation was very effective in

dissolving this oxide and the rate of dissolution decreased with the increase in Cr substitution.



19

AWC-161

EFFECT OF HIGH CONCENTRATION GADOLINIUM NITRATE IN REACTOR

MODERATOR SYSTEM

Debasis Mal, Puspalata Rajesh, S. Rangarajan, S. Velmurugan#,

Water & Steam Chemistry Division, BARCF, Kalpakkam, India


Abstract

Gadolinium is used as a neutron poison in nuclear reactors to control the reactivity

because it has high thermal neutron absorption cross section (~49,000 b) and good solubility

in water. Gadolinium nitrate is added with nitric acid to the moderator heavy water and the pH

is maintained in the range of 5.0 to 5.5 to prevent gadolinium precipitation. Usually the

concentration of gadolinium (Gd3+) used is ~15 ppm during the actuation of secondary

shutdown system. In the moderator system of a proposed tube type boiling water nuclear

reactor of Indian origin, a higher concentration (20-400ppm) of soluble neutron poison,

Gd(NO3)3 was proposed to be used in the emergency safety shutdown system. Effect of this

high concentration of gadolinium nitrate in the reactor moderator is evaluated from the angle

of generation of molecular products viz. H2 and H2O2 due to radiolysis. H2 yield was found to

increase linearly with absorbed dose (10 - 100kGy). With increasing Gd concentration there

was increase in H2 yield but the increase was marginal in 100 to 400 ppm range. Both the

initial yield and saturated concentrations of H2O2 (at higher doses) in normal and off - normal

conditions were also estimated. It was observed that the head space provided above the liquid

phase in irradiation zone has a substantial effect on the generation of H2. With decreasing

head space, H2 generation increased and went through a maximum. Production of H2O2 was

also observed to be decreased in case of fully filled samples as compared to the ~60% filled

cases. Radiolysis of Gd(NO3)3 in high purity D2O was carried out to see the isotope effect and

D2 formation was observed to be lowered than H2 for same Gd(NO3)3 concentration solutions

in light water. The above results were discussed in detail in this paper.



20

AWC-173

METAL ION IMPRINTED POLYMERS FOR EFFECTIVE RADIOACTIVE WASTE

SEGREGATION IN NUCLEAR INDUSTRY

Anupkumar Bhaskarapillai

WSCD, Chemistry Group, BARC, Kalpakkam – 603102, India


Abstract

Routine decontamination campaigns of nuclear reactors are generally effective in

removing various radionuclides such as cobalt, caesium, etc., and bring down the radiation

field. However, during some of the decontamination campaigns, the radiation field at some

surfaces were seen to have actually gone up. This was found to be due to lack of removal of

antimony isotopes by the regular ion exchange resins used, which subsequently deposited

over out of core surfaces leading to increased radiation field on those surfaces. Thus there

exists a need for efficient antimony removal system. We have earlier reported the synthesis

of nano titania impregnated - epichlorohydrin crosslinked chitosan beads, which were shown

to be capable of complete sorptive removal of antimony from its aqueous solutions of

concentration ranging from 150 ppb to 120 ppm. In this study, in order to understand the

sorption mechanism and to fine tune the bead composition, the effect of crosslinker

concentration used in the synthesis on the swelling and sorption properties of the beads was

investigated in detail. The variation effected significant changes in physical parameters such

as bead diameter, swelling ratio, equilibrium water content, and true wet density. Sorption

capacity, unlike with regular resins, was found to increase with increase in crosslinker amount.

The antimony sorption capacity of the crosslinked beads prepared by crosslinking 0.3 g

uncrosslinked beads with 6.4 mmol epichlorohydrin (crosslinker) was 493 µmol/g. Non-

crosslinked beads showed a capacity of 75 µmol/g, while the crosslinked beads made with

the least amount of crosslinker (0.64 mmol per 0.3 g beads) showed a capacity of 133 µmol/g.

These results indicate the possible involvement of the crosslinker in the sorption


21

AWC-136

CATION DISTRIBUTION IN FERRITES AND ITS EFFECTS ON THE CHEMICAL

DISSOLUTION BEHAVIOUR

P.Chandramohan#, M.P.Srinivasan and S.Velmurugan

Radiation and deposit control studies section, Water and steam chemistry division,

Chemistry group BARC, Kalpakkam Tamilnadu-603102

#Corresponding email: [email protected], [email protected]

Abstract

Ferrites are formed on the steel surfaces as a protective corrosion oxide film on the heat transport surfaces in the water cooled nuclear reactors. These oxides film acts as a host to many neutron activated corrosion products (ACPs) leading to man-rem problem during the service maintenance. Understanding of chemical dissolution kinetics of these ferrites is important aspect in the development of decontamination process with aim of good decontamination factors. Ferrite shows a cation distribution as a function of parameter like metal ion substitution, crystallite size and temperature. Change in the cation distribution in ferrite can effect its dissolution process. The following three ferrites namely CoFe2O4/ZnFe2O4/MgFe2O4 were studied for its chemical dissolution behaviour as a function of the cation distribution. CoFe2O4, MgFe2O4 and ZnFe2O4 shows an inversion parameters of 0.95, 0.46 and 0.06 respectively. The above ferrites with different cation distribution were achieved by the thermal treatment. The variation of cation distribution in ferrite was monitored/characterised by the Raman spectroscopy. Chemical dissolution of these ferrites were carried out in NAC formulation. Dissolution process was monitored by the metal ion dissolution in the solution. Dissolution data was fitted to the following two models ‘Shrinking sphere model’ and ‘Factual chain mechanism model’ to elucidate the kinetic parameter. We tried to establish correlation between the cation distribution in the ferrite and

the dissolution kinetics of ferrites. ZnFe2O4 (‘ ’= ~ 0.06) showed 𝑘𝑜𝑏𝑠(𝐹𝑒)80 = 1.250x10-3min-1 and

ZnFe2O4 (‘ ’= ~ 0.30) showed 𝑘𝑜𝑏𝑠 (𝐹𝑒)80 = 2.295x10-3min-1, indicating ZnFe2O4 with high

inversion parameter showed higher dissolution rate. Activation energy for the ZnFe2O4 (‘ ’= ~

0.30) and ZnFe2O4 (‘ ’= ~ 0.06) in NAC formulation was 58.4 and 61.5 kJ mol-1 respectively. CoFe2O4 and MgFe2O4 also showed the dependence of its chemical dissolution behaviour on the cation distribution. From the above study we could establish effect of cation distribution on the dissolution kinetic of the ferrites




22

AWC-130

AREVA’S TOOLBOX FOR LONG-TERM BEST PERFORMANCE AND RELIABLE

OPERATION OF NUCLEAR STEAM GENERATORS

Andreas Drexler#, Steffen Weiss, Neil Caris, Christoph Stiepani#

AREVA GmbH, Paul-Gossen-Str. 100, 91052 Erlangen (Germany)


Abstract

Long-term integrity and high performance of major plant systems and components are

of uppermost importance for the successful operation of any power plant. The objective of

AREVA’s asset management program is to support operators by minimizing corrosion damage

and performance losses of water-steam cycle systems and components and thereby to

maximize the availability and economic performance of the plant.

AREVA’s experience gathered with water-steam cycle chemistry treatments in more than 40

years yields the conclusion: accumulation of corrosion products in steam generators may

result in local overheating and enrichment of impurities up to critical levels. This can lead to

several degradation phenomena of the structural materials of the steam generators.

Therefore, minimization of corrosion product generation and prevention of deposit

accumulation is the one main goals of water chemistry.

The AREVA approach for long term best performance and reliable plant operation

consists of:

• Control measures (e.g. water chemistry, SG cleanliness “fouling factor”, sampling system assessment, aging management )

• Corrective measures (e.g. chemical and/or mechanical cleaning, component replacement, coating)

• Preventive measures (e.g. pH optimization, innovative additives like film forming amines, technical support for optimized plant operation )

Such asset management program is in principle a closed cycle process. A detailed technical assessment of the current situation is only a first step. In the subsequent steps appropriate measures which improve the current status or counteract on identified issues are identified and applied.

These corrective and/or preventive measures cover a wide range like improvements of water chemistry treatments, primary and secondary side mechanical and/or chemical cleanings and changes of the material concept.

This paper describes AREVA’s approach and the according field experiences of this asset management program.


23

AWC-140

TWO DECADES OF EXPERIENCE WITH STEAM-WATER CHEMISTRY

MAINTENANCE OF FAST BREEDER TEST REACTOR

K.Ganapathysubramanian, A.Suriyanarayanan≠ and B.S.Panigrahi

Reactor Chemistry Section, Reactor Operation and Maintenance Group

Indira Gandhi Centre for Atomic Research, Kalpakkam


Abstract

Fast Breeder Test Reactor (FBTR) at Kalpakkam is a 40 MWt, loop type, sodium

cooled fast reactor. The fission heat generated in the core is extracted by primary sodium

circuit and the thermal energy is transferred to non-radioactive liquid sodium in the secondary

circuit which in turn, heats Once Through-type shell and tube counter current Steam Generator

(OTSG) for producing super heated steam at 480C and 125 kg/cm2. This secondary circuit

is provided to avoid the ingress of hydrogenous materials and pressure surges reaching the

core in the event of SG tube leak. Corrosion related problems are very less in the sodium

circuits due to the absence of electrochemical reaction. The OTSG consists of four modules

each of 12.5 MWt rating. OTSG was chosen due to its higher thermal efficiency and lesser

inventory of steam/water in OTSG as it reduces the severity of sodium-water reaction, in case

of tube leak. From the point of view of corrosion and deposition, the chemistry specifications

are more stringent for OTSG than those of drum type boilers because 100 % conversion of

feed water into steam takes place in OTSG. The chemistry requirements are achieved by

providing ion exchange resin based online condensate polishing to remove ionic and

suspended impurities. Dissolved Oxygen and pH are maintained by all volatile treatment (AVT)

using hydrazine and ammonia respectively. Being a test reactor, a dump condenser with 100

% steam dump facility with cupro-nickel tubes is available for uninterrupted reactor operation

during the non-availability of turbine. Regenerative feed heating by the exhausted steam from

the turbine is also available to stage heaters and deaerator. Efficient water chemistry control

plays important role in minimizing corrosion related failures of steam generator tubes and

ensuring steam generator tube integrity. This paper describes the operational difficulties such

as premature exhaustion of CPU, impurity pick up from the system, silica excursion, online

monitoring and suitable modifications carried out in the circuit for improvement.



24

AWC-105

IDENTIFICATION OF BOILER TUBE LEAK IN RAPS-2 BY MEASURING

IODINE-134 ACTIVITY IN BOILER WATER SAMPLE OF RAPS USING OF

GAMMA SPECTROMETRIC TECHNIQUES.

P. K. Pal# and R. C. Bohra

Rajasthan Atomic power station -1&2, Kota (Rajasthan)

#Corresponding author: [email protected] (Fax 01475-242274)

Abstract

The boiler tube made up of Monel-400 of RAPS-2 has failed on few occasions. Due to

the failure of boiler tube the active heavy water enters into boiler and feed water leading to

contamination of radioactivity in secondary water circuit. The identification of boiler tube failure

was done by measuring activity of Iodine-134 in the boiler water sample using gamma

spectrometry using high purity germanium detector. In order t to increase the sensitivity of the

method 5 liters of Boiler water sample was passed through a plastic column containing 40 ml

of anion resin & 10 ml of activated charcoal to capture the isotopes of Iodine in the anion resin.

Samples were collected from all 8 Boilers of RAPS-2. The activity of I-134 was shown only

by Boiler #5. No other boilers showed any activity of I-134. This indicated that Boiler #5 had

leaky tubes. The leaky hairpin of boiler #5 was identified by measuring Tritium, IP & I-131

activity in the riser and down comer of all 10 HXs. On the basis of Trium and IP result, HX-7

was identified as leaky hairpin.


25

AWC-170

IMPROVE STEAM GENERATOR MOISTURE CARRYOVER RATE AT

MAANSHAN NPS BY CLEANING STEAM DRUM INTERNAL SLUDGE

Meng-Jen Chen

Taiwan Power Company Maanshan Nuclear Power Station

#387 nanwan Rd. Hengchung Pingtung Taiwan

Phone: +886 8 8893470~2810 Fax: +886 8 8894817


Abstract

2013 August Maanshan Nuclear Power Plant commissioned perform steam generator

moisture carryover test (MCO) and get a high rate of both unit. The reported MCO values for

the unit 2 SGs significantly higher and thus more urgent to adress , as the average MCO value

of 0.31% is substantially higher than the design limit and what is considered

acceptable(0.25%) by most turbine vendors. With both unit MCO beyond the design limit, a

plan needs to be developed to determine the cause of these high values(via an inspection of

the steam drum region of the SG , and then develop actions necessary to improved the MCO

rate).

Westinghouse made steam drum inside inspection and report, there is no obvious

regional water separator device degradation phenomena, resulting in MCO phenomenon is

due to sludge accumulation in the dryer equipment bend, causing the dryer device function is

reduced. Maanshan nuclear plant decided using chemical and join some manhand process to

remove sludge in the dryer at NOV-2013 (unit 1EOC-21). Washing steps are as follows:1.

manually remove visible mud inside the steam drum.2. Loose soaked with chemicals and

solvents to wash portion of sludge.3. Low pressure water flush with the bottom of the dryer to

remove loose sludge

Results:

Step 1 manually remove visible mud (SG A: 14kg, B: 16.5kg, C: 19.8kg)

Step2 Chemical dissolve and remove sludge from the steam generator (SG A: 149.8kg, B:

213.9, C: 248.9kg)

Step 3 flush and collect insoluble sludge (SG A: 97.3kg, B: 93 kg, C: 50.1kg)

After steam drum washing process, Maanshan NPS check the photo from micro cameras and

find most of the sludge was remove from the dryer vane pocket, but we still need to perform

MCO test to confirm the result.



26

AWC-147

ENVIRONMENTAL IMPACT OF CONDENSER EFFLUENTS INTO COASTAL

MARINE ENVIRONMENTS: NEED FOR CONTINUOUS MONITORING

V. P. Venugopal

Biofouling and Biofilm Processes Section, Water and Steam Chemistry Division,

Bhabha Atomic Research Centre, Kalpakkam, India 603102.


Abstract:

Electric plants working on the principle of steam-water cycle require large amounts of

water for condenser cooling purpose. Nuclear power plants require, on an average, about 3

m3 cooling water per minute per megawatt of electricity generated. Owning to the scarcity of

large sources of freshwater for cooling, newer power plants, particularly in water-stressed

parts of the world, tend to get located in coastal regions, where they can make use of the

abundant seawater. However, this also poses a problem, in terms of the biofouling potential

of coastal marine environments. Sessile benthic organism, which are generally present as part

of the coastal marine ecosystem, extend their habitat into the cooling water system of the

power plant. It is often observed that massive growth of such fouling organisms may endanger

normal operation of the cooling water system, unless appropriate control measures are

adopted. Presence of calcareous organisms such as mussels and barnacles in the pre-

condenser sections of the power plant is a common sight; but these organisms, when lodged

inside condenser tubes, can not only reduce the heat transfer efficiency but also can cause

localized corrosion and tube leakage, leading of ingress of seawater into the steam-water

system. It is, therefore, important that appropriate control measures are adopted to discourage

the growth of the organisms. However, this needs to be done in an environmentally

sustainable manner, as the cooling water is ultimately discharged back into the sea. The

presentation aims to give and overview of the biofouling problems generally encountered in a

typical tropical coastal power station operating in India and the chemical control measures

adopted and their effectiveness. The talk also throws light on the more recent advances in

biofouling control such as surface modification and use of nanotechnology which, in the

foreseeable future, may provide more lasting and environmentally sustainable solutions.



27

AWC-149

NANOPHASE MODIFIED FLY ASH CONCRETE WITH SUPERIOR CONCRETE

PROPERTIES, DURABILITY AND BIOFOULING RESISTANCE FOR SEAWATER

APPLICATIONS

Vinita Vishwakarmaa#, R.P. Georgeb U. Sudhaa, D. Ramachandrana, Kalpana Kumaric, R.

Preethac, U.Kamachi Mudali b and C. S. Pillaic

aCentre for Nanoscience and Nanotechnology, Sathyabama University, Chennai-600119 bCorrosion Science and Technology Group, IGCAR, Kalpakkam-603102

cCivil Engineering Group, IGCAR, Kalpakkam-603102


Abstract

There are many concrete structures in the cooling water system of nuclear power plants that are exposed to seawater in the form of tanks, pillars and reservoirs. These structures come in contact with aggressive chlorides and acid producing microbes and deteriorate by chemical and biological factors. Recently fly ash (FA) concrete has emerged exhibiting excellent degradation resistance in seawater environments. However some disadvantages are reported like lesser early strength, higher carbonation and calcium leaching. This work attempted to modify FA concrete by adding nanoparticles of TiO2 and CaCO3 for increased strength and degradation resistance. Four types of concrete and mortar mix namely fly ash concrete (FA), FA with 2% TiO2 nanoparticles (FAT), FA with 2% CaCO3 nanoparticles and FA with 2% TiO2: CaCO3 nanoparticles were cast and immersed in seawater for a year. Strength and durability were evaluated using parameters like compressive strength, split tensile test, Rapid chloride permeability test (RCPT), half cell potential test (HCP),carbonation test and pH degradation. Detailed biofilm characterizations were attempted using microbiological and molecular biology tools to study the antibacterial properties. Calcium leaching and sulfate attack studies were carried out by laboratory exposure studies. Using field emission scanning electron microcopy, EDAX and X-ray diffraction technique (XRD), microstructural properties and chemical phases were identified. All the nanophase modified FA specimens showed superior properties compared to FA concrete with respect to strength, carbonation depth, calcium leaching and antibacterial activity. Results are discussed in detail in the paper.



28

AWC-151

CONTROL OF BIOFOULING ON TITANIUM CONDENSER TUBES WITH THE

USE OF ELECTROLESS COPPER PLATING

B. Anandkumar1, R.P. George1*, D. Ramachandran2, U. Kamachi Mudali1 1Corrosion Science and Technology Group, Indira Gandhi Centre for Atomic Research,

Kalpakkam – 603102, India 2Centre for Nanoscience and Nanotechnology, Sathyabama University, Chennai – 600119,

India


Abstract

In sea water environments titanium condenser tubes face serious issues of biofouling

and biomineralization. Electroless plating of nanocopper film is attempted inside the tubes for

the control of biofilm formation. Using advanced techniques like AFM, SEM, and XPS,

electroless copper plated flat Ti specimens were characterized. Examination of Cu coated Ti

surfaces using AFM and SEM showed more reduction in the microroughness compared to

anodized Ti surface. Cu 2p3/2 peak in XPS spectral analysis showed the shift in binding energy

inferring the reduction of the hydroxide to metallic copper. Tubular specimens were exposed

to sea water up to three months and withdrawn at monthly intervals to evaluate antibacterial

activity and long term stability of the coating. Total viable counts and epifluorescence

microscopy analyses showed two orders decrease in bacterial counts on copper coated Ti

specimens when compared to as polished control Ti specimens. Molecular biology techniques

like DGGE and protein expression analysis system were done to get insight into the

community diversity and copper tolerance of microorganisms. DGGE gel bands clearly

showed the difference in the bacterial diversity inferring from the 16S rRNA gene fragments

(V3 regions). Protein analysis showed distinct protein spots appearing in electroless copper

coated Ti biofilm protein samples in addition to protein spots common to both the biofilms of

Cu coated and as polished Ti. The results indicated copper accumulating proteins in copper

resistant bacterial species of biofilm. Reduced microroughness of the surface and toxic copper

ions resulted in good biofouling control even after three months exposure to sea water.



29

AWC-155

BIOFOULING COMMUNITY PATTERN ON VARIOUS METALLIC SURFACES IN

THE COASTAL WATERS OF KALPAKKAM, SOUTHWESTERN BAY OF

BENGAL

Gouri Sahu, K.K. Satpathy*, A.K.Mohanty and V.K.Bindu

Environment & Safety Division, EIRSG, Indira Gandhi Centre for Atomic Research,

Kalpakkam-603 102, Tamil Nadu, India


Abstract

Biofouling causes great operational hazard in different marine installations across the

globe. And the expenditure incurred on combating biofouling is astounding. It is reported that

shut down of a 235 MW (e) power station due to fouling, costs about 170 lakhs (at Rs. 3.00

per kw/h) per day. Because of this economic implication, biofouling has been a thrust area of

study for the marine researchers. To assess the biofouling pattern, metallic surfaces are the

best options because of their extensive use at various installations in the marine environment.

Hence, knowledge on qualitative and quantitative aspects of biofouling with respect to metal

surfaces is of great value to design an efficient fouling control strategy. Keeping this in mind,

nine types of metal [SS-316, SS-304, MS, Titanium, Admiralty Brass, Aluminum Brass,

Copper, Monel and Cupro-nickel] panels (12 x 9 x 0.1 cm) were exposed to coastal water of

Kalpakkam from MAPS jetty at a depth of 2 m below the lowest low tide. Results indicated that

copper based panels were found to be foul-free except monel. Although, fouling settlement

was encountered on monel, the adherence was weak. Non-copper based metals showed

100% area coverage with high population density. However, in case of MS, due to exfoliation

of corrosion deposits, unevenness in fouling colonization at later stages of development took

place, though the early settlement was unaffected by initial corrosion. As expected, Titanium

showed high rate of fouling growth along with high fouling diversity compared to other non-

copper based metals. Absence of specific foulants such as, crustaceans and algae on

Titanium surface reported by others was not observed during our study. The information on

Titanium would be handy for Prototype Fast Breeder Reactor (PFBR) cooling water system

wherein, the same has been selected as condenser and process water heat exchanger

material. For non-copper based alloys including monel the fouling load ranged from 18 to 40

g. 100 cm-2. The major fouling organisms such as, barnacle, green mussel and ascidian

constituted ~ 70-80% of the total fouling. In the present study, sequence of fouling succession

was as follows, barnacle – hydroid - sea anemone – ascidian and finally green mussel (Perna

viridis Linn. 1758). The paper also discusses species diversity indices (diversity, richness and

evenness) in detail.



30

AWC-109

PLASMA NITROCARBURIZING PROCESS –A SOLUTION TO IMPROVE WEAR

AND CORROSION RESISTANCE

Alphonsa Joseph#, Ghanshyam Jhala, and S. Mukherjee

FCIPT, Institute for Plasma Research, Gandhinagar, Gujarat, INDIA.

#Corresponding author: [email protected], [email protected]

Abstract

To prevent wear and corrosion problems in steam turbines, coatings have proved to

have an advantage of isolating the component substrate from the corrosive environment with

minimal changes in turbine material and design. Diffusion based coatings like plasma nitriding

and plasma nitro carburising have been used for improving the wear and corrosion resistance

of components undergoing wear during their operation. In this study plasma nitrocarburising

process was carried out on ferritic alloys like ASTM A182 Grade F22 and ATM A105 alloy

steels and austenitic stainless steels like AISI 304 and AISI 316 which are used to make trim

parts of control valves used for high pressure and high temperature steam lines to enhance

their wear and corrosion resistance properties as shown in Fig. 1. The corrosion rate was

measured by a potentiodynamic set up and salt spray unit in two different environments viz.,

tap water and 5% NaCl solutions. The Tafel plot of ASTM A182 grade F22 steel shows that

plasma nitrocarburising for 6 and 24 hours show better corrosion resistance compared to that

of the untreated steel ( Fig. 2).

Fig. 1: Control valve components mounted Fig. 2: Tafel plot of untreated (UT)

for plasma nitrocarburizing. plasma nitrocarburized F22 steel for 6 (PNC6) and 24 (PNC24)

hours

It was found that after plasma nitrocarburizing process the hardness of the alloy steels

increased by a factor of two. The corrosion resistance of all the steels mentioned above

improved in comparison to the untreated steels. This improvement can be attributed to the

nitrogen and carbon incorporation in the surface of the material. This process can be also

applied to components used in nuclear industries to cater to the wear and corrosion problems.



31

AWC-154 FEASIBILITY STUDY OF A NON-CHEMICAL TECHNIQUE FOR FOULING

CONTROL

Yaw-Ming Chen

Industrial Technology Research Institute,

Material and Chemical Research Laboratories,


Abstract

In nuclear power plants, fouling occurred in different systems and caused operation

problems. Many factors affect the behavior of fouling. Among them, zeta potential of particles

suspended in a liquid plays an important role in deposition of particles onto surface. In our

work, a non-chemical water treatment based on the effect of zeta potential was tested to verify

its effectiveness to reduce fouling.


32

AWC-121

ENVIRONMENTAL SUSTAINABILITY BY ADOPTION OF ALTERNATE

COOLING MEDIA FOR CONDENSER COOLING

Jaymin Gandhi, Nilesh Patel

Adani Infra India Ltd.

Ahmedabad,Gujarat, India.

#Corresponding author: [email protected], [email protected]

Abstract

Water having ability to dissolve most substances and to support biological life, every

cooling water system in power plant is subjected to potential operational problems which are

mainly corrosion, scaling and biological fouling. Control of cooling water chemistry is very

critical in preventing above said problems. In view of scarcity of water and looking into the

future trends in the environment protection, water media can be replaced with air. Having such

concept in thermal & combined cycle power plants, use of Air-cooled condenser(ACC) for

Nuclear power plant may be explored. During last decade number of installations with ACC

also increased, largely in response to the growing attention being paid to environmental

concerns as well of water scarcity. The rising importance of ‘Save Water & Environment’, calls

for a broader understanding of the design and application principles involved for ACC.This

paper identifies the basic configurations of air cooled condensers used in the power industry

together with their merits & demerits when compared to those exhibited by traditional steam

surface condensers including environmental and corrosion issues. Several factors that affect

the performance of air-cooled condensers are described in detail, especially the

consequences that result from the fouling of the finned-tubes. To rectify the degradations in

performance that result from external tube fouling, a number of cleaning procedures are

described. Due to relatively high cost of sweet water and large requirement of sea water, Air

cooled condenser may become viable option in future.

Keywords: Air-cooled Condensers, Environmental aspect

mailto:[email protected],%[email protected]


33

AWC-103

RADIOLYSIS OF WATER AT HIGH TEMPERATURE AND PRESSURE

CONDITIONS: A PICOSECOND PULSE RADIOLYSIS EXPERIMENT AND

NUMERICAL SIMULATIONS

Yusa Muroya1*, Tetsuro Yoshida1, Yosuke Katsumura2,3, Shinichi Yamashita3,

Mingzhang Lin4, Takahiro Kozawa1 1 Institute of Scientific and Industrial Research, Osaka University, Mihogaoka 8-1, Ibaraki,

Osaka 567-0047, Japan 2 Japan Radioisotope Association, Honkomagome 2-28-45,

Bunkyo, Tokyo 113-8941, Japan 3 School of Engineering, University of Tokyo, Hongo 7-3-1,

Bunkyo, Tokyo 113-8656, Japan 4 School of Nuclear Science and Technology, University of Science and Technology of

China, 96 JinZhai Road, Hefei, Anhui 230026, P.R. China


Abstract

Radiolytic products of coolant material (light water) under strong radiation field in RPV

are known to give undesirable effects on nuclear structural materials. Understanding of the

fundamental processes will be of great importance on powerful support to various application

fields in water chemistry. Ionization and excitation of water molecules by ionizing radiations

initiate very fast physical and chemical processes within μs(10-6 s), ns (10-9 s) or even ps (10-

12 s), prior to formation of primary radiolytic species (e-aq, OH, H, H2, H2O2 etc.). Through the

processes, the radiation chemical yields (G-values) are supposed to change dynamically

depending on time and also on temperature. However, because of so high reactivity (short

lifetime), it was difficult to observe experimentally the temporal behaviors (spatially

inhomogeneous reactions, which is called spur diffusion reactions). In this work, the

fundamental processes (G-values of the intermediates and the fast reaction kinetics) of the

radiolysis of water at high temperature and pressure conditions were investigated by a newly

developed ultrafast (picosecond time-resolved) pulse radiolysis system, and also by numerical

analyses such as the Monte-Carlo simulation and the Spur diffusion kinetic model simulation.



34

AWC-104

INJECTION OF NANO-PARTICLES IN MITIGATING FLOW ACCELERATED

CORROSION (FAC) DAMAGE IN THE SECONDARY SYSTEM OF NUCLEAR

POWER PLANTS (NPPS)

Dong Seok Lim#, Hee Kwon Ku, Jae Seon Cho

FNC Tech., Heungdeok IT Valley, Heungdeok 1-ro, Giheung-gu, Yongin-si,

Gyeonggi-do, 446-908, S. Korea

# Corresponding author: [email protected]

Abstract

NPPs produces electric energy through phase transition of water. According to this, a

piping, which is flow path, integrity is essential for safety functions. Erosion, FAC and fittings

are corrosion failure mechanism by increasing service life. Especially, there are 10-kilometers

of piping in secondary systems. It needs to estimate FAC and apply periodic management.

Iron oxides produced by FAC cause power reduction and Loss Of Coolant Accident (LOCA)

will be occurred through the continued piping wall thinning. In this study, corrosion rate of pipe

materials with carbon steel(SA106.Gr.B) and low-alloy steel(SA335.P22) was evaluated for

pipe configuration and dissolved oxygen concentration on 150℃, pH 9.5~10.0 and flow

velocity of 5m/s. Temperature of 150℃ is well known that causes high FAC rate and pH

consider a NPPs in-service condition. Further corrosion rate test was performed to develop

FAC reduction technology through Pt-nanoparticle injection.In this study, corrosion rate is

evaluated by weight depletion method. The results of material impact assessment show that

corrosion rate of carbon steel is more higher than that of low-alloy steel because of Cr content.

And also, the results of pipe configuration test show that case with 90° elbow had maximum

wall thinning than with 180° horizontal pipe. The dissolved oxygen concentration test shows

that low oxygen condition, ≤5ppb, had high corrosion rate compared to normal condition and

the corrosion rate decreased 50% at Pt-nanoparticle injection test on maximum corrosion rate

condition compared to maximum wall thinning condition without Ptnanoparticle injection. In

this study, samples provided by each test case had analyzed through SEM-EDS(Scanning

Electron Microscopy-Energy Dispersive X-ray Spectroscopy) and XRD(X-ray diffractometer).

Behavior evaluation for oxide film was performed and Electrochemical corrosion

potential(ECP) was measured for electrochemistry evaluation. To apply Pt-nanoparticle

injection technology on nuclear power plant, study on injection conditions and methods are

on-going.

Keyword: nuclear power plant, corrosion, flow accelerated corrosion (FAC), pourbaix-

diagram, carbon steel


35

AWC-106

ADDITION OF OXYGEN IN THE INLET OF RECOMBINER UNIT IN

MODERATOR COVER GAS SYSTEM TO FACILITATE RECOMBINATION OF

DEUTERIUM AND OXYGEN TO BRING DEUTERIUM CONCENTRATION IN

SAFE LIMITS

P. K. Pal# and S. Mukherjee2

Rajasthan Atomic Power Station-1&2

PO: Anushakti, Via: Kota, Rajasthan, 323302 2STE (N), RR Site, Unit-1&2, Kota, Rajasthan


Abstract

In moderator system of a PHWR, radiolytic decomposition of Heavy Water take place

in the Calandria and D2 and O2 are formed. Since the mixture of D2 & O2 is explosive, there is

a level and various action levels for concentration of Oxygen and deuterium in moderator cover

gas. The maximum percentage limits of deuterium are 4% v/v in presence of Oxygen present

in stoichiometric ratio.

In March -2013, the deuterium concentration in moderator cover gas of RAPS-2 was

increased to 3.0 % v/v and the oxygen concentration was only 0.93% v/v which was much

less than the stoichiometric value (1.5%) . So it was decided to add oxygen in the inlet of

recombiner unit of moderator cover gas system. As in year 1999 there was fire incident in

Dalinton unit #3 due to combustion of EDPM which was used as seat material in the isolating

valve in the inlet of oxygen pressure regulating valve. EDPM has low ignition temp. So Oxygen

addition was not practiced in any other reactors.

Oxygen addition was carried out in RAPS-2 with all precaution and with proper

planning. Initially oxygen was added with very slow rate of 1 SCFH (Standard Cubic Feet per

Hour) intermittently &the process was repeated to see any harmful effect. After qualifying the

procedure, oxygen addition was done for 20 hrs at the rate of 2.5 SCFH and D2 concentration

came down to 1.95 % v/v. This paper will consists of radiolytic decomposition of D2O. The

qualification plan for O2 addition, the data of moderator cover gas and moderator system

parameters before, during and after Oxygen addition.


36

AWC-107

DETERMINATION OF MOISTURE CONTENT IN STEAMS BY ANALYZING

SODIUM CONTENT IN STEAM GENERATOR WATER & STEAMS

CONDENSATE OF A NUCLEAR POWER PLANT USING ION

CHROMATOGRAPHIC TECHNIQUE AT DIFFERENT LEVELS OF BOILER

WATER

P.K.Pal# and R.C.Bohra

Rajasthan Atomic Power Station-1&2

PO: Anushakti, Via: Kota, Rajasthan

PIN code: 323302 #Corresponding author: [email protected]

Abstract

Dry steam with moisture content less than <1% is the stringent requirements in a steam

generator for good health of the turbine. In order to confirm the same, determination of sodium

is done in steam generator water and steam condensate using Ion Chromatographic

techniques.

Depending on the carryover of sodium in steam along with the water droplet (moisture),

the moisture content in steam was calculated and was found to be < 1%, which is the

requirements of the system. The paper described the salient feature of a PHWR, principle of

Ion chromatography, chemistry parameters of Steam Generator and calculation of Moisture

content in steam on the basis of sodium analysis at different boiler levels. The moisture content

in steam increases with Boiler levels. So for smooth operation of Turbine an optimum level of

50 cm was selected for RAPS-2.

In the abstract of the paper is accepted, please acknowledge the same such that the

actual paper can be sent for publication in time. Please give the e mail id for easy and quick

communication.



37

AWC-108

EXPERIENCE ON KKNPP VVER 1000 MWE WATER CHEMISTRY

S. Ganesh, S. Selvaraj, M.R. Balasubramanian, P. Selvavinayagam#, Suresh Kumar Pillai,

Kudankulam Nuclear Power Project, Tirunelveli Dist, Tamil Nadu- 627120


ABSTRACT:

Kudankulam Nuclear Power Project consists of pressurized water reactor (VVER) 2 x 1000

MWe

constructed in collaboration w*ith Russian Federation at Kudankulam In Tirunelveli District,

Tamilnadu. Unit #1 attained criticality on July 13th 2013 and the unit was synchronized to grid

on 22nd October 2013.This paper highlights experience gained on water chemistry regime for

primary and secondary circuit.

Primary Circuit:

Primary circuit is a weekly Alkaline, reducing, Ammonia and Potassium water

chemistry coordinated with Boric Acid.

The structural material of reactor pressure vessel is low alloy steel 15X2HMФA (C‐

0.15%, Cr‐2%,Ni‐1%, Mo‐ <1.0%, V‐<1.0%) cladded with austenitic stainless steel

08X18H10T (C‐0.08%, Cr‐18%, Ni‐10.0%, Ti‐ <1.0%). The other pipelines are low alloy steel

cladded with austenitic stainless steel.

One of the special features in the primary circuit of KKNPP is that four high temperature

titanium filters are connected across reactor coolant pump to remove undissolved activated

corrosion impurities. KOH is added as an alkalizing agent instead of LiOH to maintain pH in

the primary circuit. This is being carried out to prevent tritium build up in the primary circuit.

Ammonia is being added to maintain the dissolved oxygen and dissolved hydrogen to maintain

reducing condition in the primary circuit. The control parameters and diagnostic parameters

stipulated in the design are to ensure the design service life of the primary system equipments,

low radiation build up on the out of core surfaces, minimum deposition and oxidation on the

fuel clad. The experience on water chemistry of primary circuit is elaborated in this paper.

Secondary Circuit:

The structural material of SG body and collectors is of low alloy steel (perilitic class

steel) 10GH2MΦA (C‐0.1%, Ni‐2%, Mo‐<1.0%, V‐<1.0%). Collectors are cladded internally

with corrosion resistant austenitic stainless steel. Steam Generator, Low and high Pressure

heater tubes are made of austenitic stainless steel, 08X18H10T (C‐0.08%, Cr‐18%,Ni‐

10.0%,Ti‐ <1.0%). Steam Generators are horizontal which is unique in KKNPP provide

saturated steam with very low moisture carry over. Online Cationic conductivity

measurement to find out trace level impurity ingress into condensate system is also an unique

feature in KKNPP. Secondary circuit pH and low dissolved oxygen is maintained by addition

of ammonia and hydrazine hydrate respectively. The main objective of secondary water

chemistry is to minimize the deposition and corrosion of the SG tube which is 3rd barrier in

the defense in depth. Full flow condensate polishing unit and continuous SG blow down

purification systems ensures the secondary water chemistry. The experience on water

chemistry of secondary circuit is also elaborated in this paper.



38

AWC-110

KINETICS OF DISSOLUTION OF NI-CR CONTAINING IRON OXIDES SERIES

(NICRXFE2-XO4) IN HMNO4 MEDIUM

V. Balaji a, P. Chandramohan a, Ashish Tiwari b S. Rangarajan a, S. Velmurugana#

aWater And Steam Chemistry Division, BARC Facilities, Kalpakkam - 603102, India

bChemistry Division, Trombay - 400085, India #Corresponding author: [email protected]

Abstract

The oxide film formed on steels in water–cooled nuclear reactors, has a duplex layer

structure with an inner and outer layer of different composition and different microstructure.

The films formed under Hydrogen Water Chemistry (HWC) are considerably thinner than those

formed under Normal Water Chemistry (NWC). Ni-Cr ferrite is one of the important corrosion

products formed on the structural material of steels in water–cooled nuclear reactors. The

increase of chromium in the inner layers enhances the stability of the oxide. The dissolution

of mixed oxides is considerable importance in terms of reducing radiation fields. In order to

understand the mechanistic aspects of decontamination, a series of chromium substituted

nickel ferrites with chemical composition NiCrxFe2.0-xO4 (0 x 2.0 in steps of 0.2) were

prepared through sol-gel combustion route using different amounts of metal nitrates and

urea/citric acid as the starting materials. The oxide precursors were annealed at 773 ± 5K for

4 h. The XRD and Raman patterns indicated that the synthesized oxides have single-phase

spinel structure with crystallites in nano-size range. The oxidative dissolution of Ni-Cr ferrites

were carried out in 3.0 mM HMnO4 medium at 363 ± 5K as a function of chromium substitution

in the lattice. The rate constants were determined using both inverse cubic rate law and a

general kinetic rate law models. The GKE model yields higher factor of increase, compared to

ICR model. A similar trend of increasing rate constants as estimated by Ni /Cr release for the

Cr-Ni ferrite (0.2 x 2.0) by both ICR and GKE models were also observed. The kinetic data

on Ni-Cr ferrites dissolution in solution of HMnO4 were also analysed in terms of chain

mechanism model which takes into account the changes in the fractional dimension of the

surface of dissolving particles.


39

AWC-111

MEASUREMENT OF HENRY’S LAW CONSTANT IN HYDROGENATED

LIOH/H3BO3 SOLUTION

E. H. Lee, G. G. Lee, D. H. Lee, and D. H. Hur

Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, 1045

Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of Korea

Corresponding author: [email protected]

Abstract

In pressurized water reactors, hydrogen is added to the reactor coolant system in order

to reduce the oxidation of water by radiolysis and to maintain reducing conditions. The

dissolved hydrogen concentration in pressurized water reactors has been controlled within the

range of 25~50cc (STP)/kg-H2O. It is well known that the dissolved hydrogen leads to primary

water stress corrosion cracking. Therefore, the optimization of the hydrogen concentration in

the reactor coolant system is regarded as one of several effective approaches to manage the

material integrity and reduction of the radiation sources in the primary circuit. In order to predict

the content of the dissolved hydrogen, it is needed to measure and monitor the content of the

dissolved hydrogen accurately. In this work, the Henry’s law constant was experimentally

determined in hydrogenated LiOH/H3BO3 solution. The Henry’s law constant was calculated

from in-situ mesaurements of the hydrogen fugacity on the inside of the Pd-Ag tube for

temperatures between 290℃ and 330℃ at pressures between 2000 psia and 2900 psia. The

Henry’s law constant were found to decrease linearly with increasing temperature and with

decreasing pressure. The observed trend in the Henry’s law constant corresponded well with

other workers’, however, the absolute values were different from literature data. This may be

due to the effect of vessel pressure on the hydrogen fugacity and the accuracy of the

measuring sensor. To better calculate the Henry’s law constant, the pressure and the content

of the dissolved hydrogen should be considered. In this work, the effects of temperature and

pressure on the Henry’s law constant are described by an empirical model based on the

experimental data. This emprical model is compared with other literature data.



40

AWC-116

SEASONAL VARIATION IN TRIHALOMETHANE LEVELS AT KALPAKKAM

AND IN RELATION TO ORGANIC CARBON PRECURSORS

R. Rajamohan1, V. P. Venugopalan#1 and Usha Natesan2 1Biofouling and Biofilm Processes Section, Water and Steam Chemistry Division

Bhabha Atomic Research Centre, Kalpakkam, Tamil Nadu 603 102, India 2Centre for Water Resources, Anna University, Chennai, Tamil Nadu 600 025, India


Abstract

Biofouling control in coastal power stations is generally achieved through the use of

chlorination. However, chlorine reacts with natural organic matter, leading to the formation of

several chlorinated by-products such as trihalomethanes (THMs). Environmental discharge of

THMs is of concern, as these compounds have been reported to be carcinogens and

mutagens. Madras Atomic Power Station (MAPS) employs continuous gas chlorination for

controlling biofouling. Several studies have shown that the formation of THMs depends on

several parameters, including the concentration of chlorine, total organic carbon (TOC),

bromide, water temperature and pH. This study discusses the seasonal variation of TOC and

compares it with the levels of chlorine residual in the formation of THM in the cooling water

circuits of MAPS. The study showed that the more THM concentration was formed during the

period when more concentration of chlorine was dosed and the formation of THM showed

more correlation with the levels of chlorine than total orgainc carbon.

Keywords: Chlorination by-products, Trihalomethanes, Total organic carbon, Total residual

chlorine


41

AWC-117

ROLE OF REDUCTANTS IN CORROSION CONTROL OF MATERIALS

RELEVANT TO NUCLEAR REACTORS

Padma S.Kumar1, Sinu Chandran1, Puspalata Rajesh1, D.Mohan2, S.Rangarajan1 and

S.Velmurugan#1

1Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, Tamilnadu, India 2Membrane Lab, AC Tech., Anna university, Chennai, Tamilnadu, India


Abstract

Presence of oxidants aggrevate corrosion of materials in aqueous medium. Removal

of dissolved oxygen from aqueous systems of steam generating power plants, boilers etc. and

inhibition of corrosion of component materials become very essential. Reductants like

hydrogen gas or water soluble reducing agents can be used to control the corrosion and

protect the structural components. Feasibility of using alternate reductants such as hydrazine,

ammonium hydroxide and hydroxylamine which stays in liquid phase is studied in this paper.

A comparative study of corrosion behavior of the materials Carbon steel, Stainless steel(SS-

304 LN), Monel-400 and Incoloy-800 in the oxidative and reductive conditions are being

discussed. In nuclear industry, water radiolysis products like H2O2 is responsible for corrosion.

Computation on the generation of oxidizing species (O2 and H2O2) and their distribution in

steam and water phase were made. Analytical methods have been standardized to study the

distribution of hydrazine, ammonia, hydroxylamine and hydrogen peroxide. Extensive studies

were carried out at 90oC, 150oC to study the compatibility of structural materials in the oxidative

and reductive environments. Electrochemical evaluation at 90oC showed that these reductants

were very efficient to control corrosion of materials. Studies in HTHP system at temperature

range 200 – 280oC evaluated the thermal stability of reductant hydrazine and its effect on

redox potential of SS-304 LN. There was potential change from -0.4V (versus SHE) to -0.67

V (versus SHE) on addition of 5 ppm hydrazine at 240oC. The decomposition rate of hydrazine

was observed to follow first order decay. As these reductants can be used in nuclear reactors,

the radiation stability also was studied. The distribution of the oxidant hydrogen peroxide and

the reductant hydrazine was found to be comparative in water-steam phases. The surface

morphology of the exposed structural materials at high temperature were characterized by

surface techniques such as SEM, EDX, RAMAN spectroscopy and by optical microscope.


42

AWC-119

IMPROVEMENT IN PERFORMANCE OF DM PLANT, SECONDARY SYSTEMS

FOR ACHIEVING CHEMISTRY PERFORMANCE INDICATOR OF KGS-3&4

B.S.Sahu#, P.G.Raichur, M Srinivas and M P Hansora

Kgs- 3&4, NPCIL, Uttar Kannada, Karnataka, India.


Abstract

Kaiga Generating Station (KGS)-3&4 has two 220MWe Pressurized Heavy water

Reactors. It uses Heavy water as moderator and coolant and DM (De-mineralized) water in

secondary system for steam generation. Raw water for plant is taken from Kali River. Raw

water is first treated in pretreatment plant and Dual media filter for turbidity removal.

Chlorination is carried out for control of micro-organism. DM water is makeup to feed water

which is the input to Steam Generator for production of steam for power generation.

Continuous blow down through Boiler blow down (BBD) IX column is carried out to control

Steam Generator (SG) chemistry.

It was decided by NPCIL to calculate Chemistry Performance Indicator of KGS secondary

and first time it was found 2.6 which was much higher than Standard and best achievable

value of 1.0. Detailed analysis was carried out and improvements for DM plant, water

treatment plant, BBD IX column, Steam Generator etc were identified.

Turbidity of filter water was brought below 2.0 NTU. Many changes were incorporated in DM

plant. Regenerate concentration, regeneration levels and regeneration procedures were

modified. Resin replacement frequencies were fixed and brine treatment of anion resin was

started at regular interval. For DM water production two mixed resin columns in series were

used in place of earlier one mixed resin column. By these modifications DM water Chloride,

Sodium and Sulphate were brought <1.0ppb from earlier 5-10ppb.

Regeneration procedure of BBD IX column were standardized. Service life of BBD IX column

was fixed and was isolated from service before complete exhaustion. Design deficiencies of

BBD IX column was rectified by applying innovative idea. Online sodium analyzer war installed

in boiler blow down line.

By implementing these improvements Chemistry Performance Indicator of both units were

brought down to 1.0, which is standard and best achievable value.



43

AWC-120

EXPERIENCE OF CHEMICAL TREATMENT FOR CONTROLLING CORROSION

IN IDCT WATER OF KGS 3&4.

V. Uday Kumar & B.S.Sahu#

KGS- 3&4, NPCIL, Uttar Kannada, Karnataka, India.


Abstract

KGS (Kaiga Generating Station)-3&4 is 220MWe pressurized heavy water reactor.

Active Process Water Cooling system (APWC) cool active process cooling water through

plate type heat exchanger. The heat from this system is dissipated to the atmosphere through

Induced Draught Cooling Tower (IDCT). Continuous make up of system is carried out with

raw water to compensate evaporation and blow down loss. Average Langlier Index (LI) of

makeup water is -2.0. Cycle of concentration (COC) of APWC system water is around 4.0

and LI at this COC is around -0.1. As per design chlorination of water is carried out and 0.2-

0.5ppm free residual chlorine (FRC) is maintained. Other than chlorination no chemical

treatment was considered in the design.

Considering that cooling water may have corrosion, scaling and bio-fouling problems,

a detailed study was carried out. Corrosion, scaling and bio-fouling studies were carried out

for three months by maintaining the COC around 4.0 & during this period normal chlorination

was carried out. The results of the study had shown high corrosion rate for Carbon Steel (CS)

but water did not have high scaling & the bio-fouling tendency. Sulphate Reducing Bacteria

(SRB) and Total Bacteria Count (TBC) were evaluated & found within the limits. This indicated

that water is corrosive in nature & a suitable chemical treatment needs to be carried out to

control the corrosion of cooling water system.

Chemical treatment in IDCT water with the formulation consisting of Zinc,

Phosphonate, Azole and low molecular formulation was started along with chlorination.

Biocide (Benzalkonium chloride) dosing was also started at regular intervals. After chemical

dosing a downtrend trend of corrosion rate of CS was observed but still it was higher than

limit. After increasing Zinc concentration in water from 0.2 to 0.5 ppm, CS corrosion was

reduced to <2.0.



44

AWC-122

ELECTROCHEMICAL PASSIVATION STUDIES OF ZIRCALOY IN PRESENCE

OF METAL ION

Sinu Chandran, H. Subramanian, N. Sreevidya*, S. Rangarajan# and S. Velmurugan

Water and Steam Chemistry Division, BARC Facilities, IGCAR Campus

Kalpakkam, Tamilnadu, INDIA Telefax: +91 44 27480097

*MJS, MTD, Indira Gandhi Centre for Atomic Research

Kalpakkam-603102 Tamilnadu, INDIA

#Corresponding author:[email protected]

Abstract

Inorganic metal ion additives are being explored for controlling the corrosion and

deposition of activated corrosion products on out of core surfaces in Pressurized Heavy Water

Reactors. Addition of Mg2+ to the process stream is reported to be beneficial in reducing

corrosion and corrosion product release from carbon steel. This added Mg2+ ions can modify

the oxides on other heat transfer surfaces and thus influence their corrosion behavior. In this

context, an attempt was made to study the role of Mg2+ ions in modifying the passive films on

Zircaloy surfaces by electrochemical passivation at ambient temperatures. Increased

polarization resistance obtained from the impedance spectra recorded at OCP in the presence

of Mg2+ ions revealed the beneficial effect of Magnesium. Different passive potentials were

identified from the passive regions of the polarization curves. Each potential was applied to

the specimen surface and the film growth was monitored by amperometry as well as by

obtaining time evolution impedance spectra. The extent of Mg uptake in the oxide was

evaluated by different surface characterization techniques. The results obtained from the

above studies are discussed in detail in this paper.


45

AWC-123

OXIDATION/CORROSION COMPATIBILITY STUDIES OF P91 AND RAFM

STEELS BY ELECTROCHEMICAL TECHNIQUES

N Sreevidya, Sinu Chandran*, C.R. Das, S. K Albert#, S Rangarajan* and S Velmurugan*

Material Technology Division, Indira Gandhi Centre for Atomic Research

Kalpakkam-603102 Tamilnadu, INDIA

*Water and Steam Chemistry Division, BARC Facilities, IGCAR Campus, Kalpakkam-

603102,Tamilnadu, INDIA


Abstract

Oxidation behavior of Reduced Activation Ferritic Martensitic (RAFM) steel, the

structural material for fusion reactors exposed to atmosphere for a period of ~6480 hrs has

been studied giving special emphasis on the morphology and chemistry of the oxides formed.

The results obtained are compared with those of Grade 91 (P91) steel from which the RAFM

steel has been evolved mainly by replacing Mo and Nb with W and Ta respectively. RAFM

corrodes faster than Grade 91 steel. Presence of chloride ions has a major role in deteriorating

the corrosion resistance of RAFM steel. The oxides formed in both the materials consist of

binary oxides of Fe and Cr, hematite, magnetite, chromia and Fe-Cr spinel oxides. Corrosion

of these steels has also been studied by electrochemical techniques that confirm the inferior

corrosion resistance of RAFM steel compared with that of Grade 91steel



46

AWC-124

PERFORMANCE RESTORATION TECHNIQUE DEVELOPED FOR FOULED

HEAT EXCHANGER

Dipankar Nanda1, Babloo Tiwari2, R. M. Pandey3#,

Coolant Systems Lab (CSL)

Raja Ramanna Centre for Advanced Technology, Indore, India


Abstract

Heat exchanger (HE) is one of the important equipment of installations for satisfactory

operation of power plants, chemical plants, Accelerator machine etc. The performance of HE

depends on the material of construction (MOC) as well as good engineering practice adopted,

and performance deterioration takes place due to surface deposition, making it a thermal

insulator.

In Indus-2 Electron Synchrotron Accelerator, RRCAT, the Plate Heat Exchanger (PHE) are

installed to dissipate heat from primary process coolant (deionised water) to secondary cooling

tower coolant (soft water) through parallel narrow passage of SS 316 corrugated HE plates.

For achieving precise accerator beam stability, the process cooling water temperature stability

is required to be maintained within ±10C. Deposition of scale takes place in secondary side of

HE as Saturation Index (SI) is maintained at + 0.5. This affects the heat transfer coefficient.

Hence, routine cleaning is required to remove the calcite scale of HE, leaving behind

protecting layer of calcium carbonate scale on pipeline and other wetted parts of the loop to

prevent corrosion.

Unavoidable circumstances led to hard deposition of scales and the problem could not be

even addressed by experts in this field. Samples were systematically analysed in the CSL

laboratory to know the content of the deposit so that suitable method could be applied to

selectively remove the foulants to finally clean the HE. About 48.52 % of deposit was found to

be acid soluble, whereas approximately 44.14% of deposit dissolves in alkali. The remaining

7.43% residue was neither dissolved in acid nor in alkali which indicates that the undissolved

part may be mostly of dust.

The cleaning solution was formulated in-house to remove the scale from heat exchanger

plates. Sulfamic acid solution at 800C was used to decompose calcium scale to liberate carbon

dioxide, whereas sodium hydroxide solution with EDTA was used to remove remaining scale.

The performance of the heat exchanger was restored. The developed formulation is believed

to be most effective for all heat exchangers used in water application.

Keywords- Accelerator, Low Conductivity Water Plant, Heat Transfer, Chemical Cleaning



47

AWC-125

NITROGEN COMPOUNDS FORMATION IN N2-WATER AND N2-MOISTURE

SYSTEMS

G.R. Dey# and T.N. Das

Radiation & Photochemistry Division, Bhabha Atomic Research Centre

Trombay, Mumbai 400085


Abstract

The generation of nitrogen compounds such as NO, NO2, NO2- and NO3

- in aqueous

and gas phase present in a high ionizing radiation zone is normal phenomena. Their formation

mechanisms, and the control processes still pose a challenge with reference to the resulting

corrosive environment and its effect on the structural materials used in nuclear industry. The

source of nitrogen for these products is mainly from air ingress to the system, and/or the

nitrogen compounds such as amines mostly used to control dissolved oxygen. These amines

such as ammonia, hydrazine, volatile amines are used in different parts of the nuclear power

plants for different purposes viz. pH control, and dissolved oxygen scavenger in coolant or

moderator systems. During their uses under high radiation environment N2 and these nitrogen-

containing compounds receive low to high doses that affect the compounds’ subsequent

chemistry and possibly generate these N-O compounds.

With this concern our objective was to study the radiation chemical effects of nitrogen (air

ingress), and more recently in nitrogen–moisture cold plasma system. Cold plasma is an

electric discharge in presence of dielectric surface(s) such as pyrex, quartz and alumina to

produce excited state species, charged species, free radicals and photons near room

temperature and atmospheric pressure. Moreover, in N2-moisture cold plasma systems, ozone

was not observed as product whereas the absorbance at 204, 214, 226 and 400 nm were

observed in gas phase UV-vis spectrophotometric measurements due to NO2 formation. In

this presentation a summary of the results on various aspect of the formation of different N-O

compounds during radiolysis of aqueous systems as well as in gas phase cold plasma will be

discussed.


48

AWC-126

EVALUATION OF ALUMINUM BRASS COUPONS IN BWR CONDENSATE

ENVIRONMENT IN PRESENCE OF METAL IONS

K K Bairwa1, V S Tripathi1#, A Kumar2 and D B NaiK1

1: Radiation & Photochemistry Division, Bhabha Atomic Research Centre, Mumbai-

400085, INDIA

2: Chemistry Division, Bhabha Atomic Research Centre, Mumbai-40085, INDIA


Abstract

Effect of cobalt and cesium ions in the simulated BWR condensate environment (two

phase water at 150 oC) on the oxide formed on the aluminium brass has been studied by

exposing active and prepassivated coupons in respective environments. Surface changes in

the exposed coupons were evaluated by SEM, EDAX and electrochemical studies. The SEM

and EDAX data of the exposed coupons indicated marked difference in the surface

morphology with varying water chemistry. Presence of nodular grains were seen on SEM

images of the pre-passivated Al brass coupons in the Co based media while more granular

oxide formation could be seen in presence of Cs. With the mixture of Co and Cs, oxides with

larger particle size were seen in the SEM images. The weight change measurement also

indicated that Co affects the outer oxide layer to a higher extent as compared to Cs. EDAX

measurements indicated incorporation of Co in the oxide layer for the coupons exposed in the

Co based media whereas higher aluminum composition was seen in the oxide layer for the

coupons exposed in the Cs based media. Cathodic reduction of the oxide layer in sodium

perchlorate medium indicated that the oxide grown in only water based media are primarily

Cu2O with a minor amount of ZnO but there is a significant amount of Co in the oxide layer for

the coupons exposed in the Co based medium. Impedance measurement of the coupons

indicated similar protective nature of the passive layers formed under various conditions based

on the values of charge transfer resistance obtained by fitting the experimental data to the

Randles circuit. However, the higher capacitance values for oxides formed in the Co based

medium indicated its porous nature. Thus, there is significant sorption of Co in the passive

layer of the aluminium brass while there is no evidence of Cs sorption over aluminium brass

could be obtained in the present study.


49

AWC-127

SYNTHESIS AND CHARACTERIZATION OF V(HCOO)2·2H2O

V S Tripathi1#, K K Bairwa1, S N Achary2 and D B NaiK1

1: Radiation & Photochemistry Division, Bhabha Atomic Research Centre, Mumbai-

400085, INDIA

2: Chemistry Division, Bhabha Atomic Research Centre, Mumbai-40085, INDIA


Abstract

Decontamination of light water reactors wherein stainless steel is used as major

structural material involves removal of various substituted ferrites with high lattice energies.

Strong reducing agents such as V (II) and Cr (II) are known to be very effective in reductive

dissolution of such oxides. The stringent requirement of inert condition poses immense

handling related issues for the large scale application of these formulations which can be best

overcome by application of their solid compounds. Solid V(II) formate has been synthesised

and characterized in this regard. In situ generated vanadyl formate has been reduced with Zn

amalgam at high concentration (350 mM). The brown precipitate obtained by the chemical

reduction has been found to be a V(II) compound with partial solubility in water. However this

compound could be dissolved in equimolar formic acid solution. The UV visible spectra of the

the re-dissolved compound indicated the presence of V(II) species. The chemical formula of

the compound was established by combination of compositional analysis, FT-IR,

thermogravimetry and XPS analysis to be V(HCOO)2·2H2O. Reducing a V(V) precursor led to

zinc substituted product formation which could be avoided by using the V(IV) precursor. The

phase analysis of the compound was done to get some insight into its structures. The

observed XRD data was indexed and the unit cell parameters thus obtained were refined by

the least square method. Monoclinic unit cell parameters obtained for the V(II) compound have

similarity with the various reported M(II) formate di-hydrate (M = Cu, Zn, Fe).


50

AWC-129

STUDIES ON FAILURE ANALYSIS OF STAINLESS STEEL ION EXCHANGE

HOPPER AT NAPS

Ranjana Kusari, S.K.Upadhyay# and Brij Mohan

Narora Atomic Power Station

Nuclear Power Corporation of India Limited


Abstract

Moderator and PHT purification system is designed to remove the ionic impurities as

well as radioisotopes from the Moderator & PHT system. The ion exchange hopper contains

deuterated nuclear grade resin (MB H+ for Moderator and MB Li for PHT system) filled in

stainless steel hoppers. Same column is used either in Moderator or in PHT system based

on the type of resin charged. Stainless steel ion exchange hoppers made of SS plate

(SS304L) with 6mm thickness and capacity 135 litres are used in Moderator and Primary Heat

Transport system ion exchangers. These Stainless Steel hoppers were being used for the

past 24 years. Gradual increase in tritium DAC was observed in the purification building. The

ion exchange column was isolated one by one for identification of leakage. DAC has gradually

decreased after isolation of the ion exchange column at the leaky pits.

The suspected leaky columns which were isolated were removed from location, then

these columns were decontaminated visual inspection reveals pitting mark on the column. A

portion of the most leaky hopper SSH#10 was cut for investigation. Stereoscopic

observations, revealed the type of cracks which was transgranular in nature. The cracks were

observed to propagate from outer surface to inner surface. A cut portion of hopper#10 was

sent to BARC for further investigation. Upon thorough studies, it was revealed that the failure

might be due to iron embedded stress corrosion cracking. This is a generic problem, as found

in several ion exchange column.


51

AWC-131

ANTIMONY (Sb) SORPTION AT HIGH TEMPERATURE AND PRESSURE ON

ZIRCALOY, CARBON STEEL (CS) AND MAGNETITE COATED CS (MCS)

SURFACES

S. J. Keny1, B. K. Gokhale1, A. G. Kumbhar1#, Santanu Bera2, Saibal Basu3,

S. Velmurugan2

RPCD1, WSCD2, SSPD3 Bhabha Atomic Research Centre, Trombay, Mumbai – 400 085

(INDIA) * Corresponding author: [email protected]

Abstract

In Pressurized Heavy Water Reactors (PHWRs), due to aggressive conditions Sb from

PHT (primary heat transfer) pump bearings, releases into the reactor core and gets activated

to 121Sb and 123Sb. Subsequently, it deposits on out of core surface resulting in radiation

exposure to station personnel’s and apparent high decontamination factors. Sb, thus

deposited can’t be removed by normal decontamination process. To simulate reactor

conditions CS/ MCS/ zircoloy coupons along with Sb metal were exposed to pH 10.20 solution

(LiOH) at 280˚C (70-75 Kg/Cm2) in a Teflon coated static autoclave for 30 days. The GIXRD

of zircaloy exposed coupons showed the peak position at 2θ ~28.4, 40.5 and 45.5, specifies

the presence of Sb as Sb2O4 creating a separate phase on the surface. Whereas weak signal

of Sb oxide formation were observed on CS and Magnetite CS surfaces. Released of Sb into

the solution in the presence of Zircaloy was found to be maximum (57 ppm) as compared to

the CS (28 ppm) and magnetite CS (17 ppm) coupons in the solution. XPS studies indicated

very less (2%) incorporation of Sb in CS compared zircaloy (9%) and MCS (14%). This shows

that on bare CS surface Sb may not be finding the way due to competition with magnetite

formation. Whereas on already formed magnetite major part goes as Fe2+ substitution and on

zircaloy it deposits as separate Sb2O4 phase. In all the cases, binding energy of Sb 3d3/2 was

found in the range 539.7 – 540.1 eV which indicates the presence of Sb in 3+ state. This study

may be useful in developing a formulation for Sb decontamination and reduce Man Rem

expenditure in nuclear power plants.

mailto:agk@barc.


52

AWC-132

EFFECT OF ANTIMONY(III) ON CARBON STEEL CORROSION INHIBITION BY

MOLYBDATE IN CITRIC ACID SOLUTION

Vinit K. Mittal, Y. Raghavendra, Santanu Bera, S. Sumathi, S. Rangarajan, S.V. Narasimhan

and S. Velmurugan

Water and Steam Chemistry Division

BARC Facilities, Kalpakkam 603102, Tamil Nadu

Abstract:

Molybdate is known as a good corrosion inhibitor of carbon steel (CS). But it cannot

inhibit CS corrosion in citric acid solution at 85oC. It has been observed that the presence of

small concentration of Sb(III) along with MoO42- inhibits CS corrosion efficiently. The

corrosion inhibition by MoO42- have been studied extensively by varying the concentration of

Sb(III) and MoO42-. A critical concentration of MoO42- is required to passivate CS in acid

medium in the presence of Sb(III). The study shows that molybdate forms a thin protective

layer on CS surface in presence of Sb(III) which provides the corrosion inhibition. Inhibition

property and the layer composition on CS surface have been studied by electrochemical and

surface analytical techniques. The protective layer is found to be composed of both Mo and

Sb and appears to be formed due to cathodic reduction of Mo6+ to Mo5+ & Mo4+ and anodic

oxidation of Fe and Sb.


53

AWC-134

RADIOACTIVE LIQUID WASTE DISCHARGE REDUCTION STRATEGIES AT

TAPS 1&2

Deepa Papachan#, A.K.Panda, S.M.Maskey, M.Joshi, V.S.Daniel

Technical Services Section, Tarapur Atomic Power Station 1& 2


Abstract

Tarapur Atomic Power Station -1&2 (TAPS-1&2) consists of twin unit of Boiling Water

Reactors (BWR) and is located at Tarapur in India. The radioactive effluent release from the

station is regulated by Atomic Energy Regulatory Board(AERB) in India. Based on the

decreasing trend of radioactive liquid waste discharges over a period of a decade, which was

within the previously stipulated limits so as to restrict the outside population to receive a

radiation dose less than1mSv/year from all type of radioactive releases, it has further brought

down the discharge limits. Over the period TAPS1&2 has reviewed the pattern or source of

liquid waste generation and the waste treatment processes incorporated at the Station and at

Waste management facility (TRAP) affiliated to the station and has been able to bring down

the liquid waste discharges to as low as possible within the available infrastructure and

financial constrictions.

This paper discusses the evolution in the liquid waste management strategies at

TAPS1&2 for the past eight years and compares with the international trends and practices to

chart out the future course of action.


54

AWC-135

EVALUATION OF ADVANCED HOT CONDITIONING PROCESS FOR PHWRS

P.Chandramohan#, M.P.Srinivasan and S.Velmurugan

Radiation and deposit control studies section, Water and steam chemistry division,

Chemistry group BARC, Kalpakkam Tamilnadu-603102

#Corresponding email: [email protected], [email protected]

Abstract

Hot-conditioning/hot functional test process is carried out to the PHT system of reactor

before reactor going to critical/operational. The process is aimed in checking the component

functionalities at high temperature and high pressure conditions, the process also checks/

removes the suspended corrosion products in heat transport circuit. This process leads to

formation of a passive or corrosion oxide film on the heat transport circuit surfaces which

protects/mitigates the corrosion of the system circuits during the operation of plant. Major

concerned alloy in the Primary Heat Transport (PHT) system of Indian PHWRs during the hot

conditioning process and also during operation is the carbon steel due to its high corrosion.

Hot-conditioning process mitigates the corrosion of carbon steel by the formation of iron oxide

(Fe3O4) as major oxide phase layer on the carbon steel surface with a typical thickness of 1.0

µm with particle size of 1µm after 336h of process at 250 C. But this passive oxide film

thickness increase with time of operation of system with c.a. 10µm for 2.2 EFYP. The

protectiveness of passive layer can be further enhanced by reducing the particle sizes in the

passive film to nano meter range. The process can impact on the compactness of passive

oxide layer with reduced pores in the oxide layer and properties of the nano nature oxide

(transport properties) impacting the corrosion mitigation. The corrosion mitigation reduce the

source term in the activated corrosion product generation.

To achieve this a new process ‘Advanced hot conditioning’ was developed in water

steam chemistry division, BARC for getting a passive oxide film with a lowered particle size in

the passive film. The AHC process with 1g/L of PEG-8000 at 250 C for 336 h showed a

particle size 100nm. The process was tested under the normal operating conditions as

function of the time, the corrosion parameter like oxide film thickness, corrosion rate and metal

ion release to the solution as corrosion products showed improved results for the AHC

process. The studies also focused applicability of the above process at high temperature like

260 and 280 C.




55

AWC-137 .

TREATMENT OF FAST REACTOR LIQUID WASTE- ELECTROCHEMICAL

METHOD

Swapan Kumar Mahato1, R. Sudha1#, P. Muralidaran2 and S. Anthonysamy1

1 Chemistry Group, 2 Reactor Operations and Maintenance Group

Indira Gandhi Centre for Atomic Research

Kalpakkam 603 102, Tamil Nadu, India


Abstract

During the operation of fast reactors, components get wetted by sodium. The sodium

wetted primary components such as pumps and intermediate heat exchangers (IHX) in fast

reactors are cleaned free of sodium followed by suitable chemical decontamination process

before taking them for maintenance or for disposal. This helps in reduction of radiation dose

to the operating personnel. Sodium cleaning and decontamination generates large volumes

of liquid effluent. The major activity in the liquid effluent during sodium

cleaning/decontamination is de to Na-22, Mn-54, Co-58, Co-60, Fe-59, Cs-137 and Cs-134.

It is required to chemically treat the effluent to reduce the activity levels prior to storage in

tanks and transportation to the waste management facility for final disposal. Conventionally

the ion exchange method is used for removal of radionuclides which produces large quantities

of secondary waste. A method which is suitable both for removal of radionuclides present in

low concentration and that avoids generation of large quantities of secondary waste is

required. Hence an electrochemical method for metal ion removal is attempted in this work

which produces little or no secondary waste. Electrochemical method towards removal of

manganese ions was finalized earlier using reticulated vitreous carbon (RVC) from simulated

decontamination solution containing a mixture of sulphuric and phosphoric acids. In

continuation of the experiments for the removal of cesium ions from simulated cleaning

solution which has an alkaline pH, a thin film of nickel hexacyanoferrate (NiHCF) was

deposited electrochemically on the surface of RVC. Hexacyanoferrates are known for

selectively binding cesium. This NiHCF coated RVC was used for electrodeposition of Cs ions.

NiHCF coated and Cs deposited RVC was characterized using SEM/EDS analysis. EDS

analysis confirms the presence of Cs on NiHCF coated RVC.



56

AWC-138

FIXATION OF NUCLEAR WASTE INTO GLASS MATRICES FOR ULTIMATE

DISPOSAL

G. Hazra1#, T Das1 and P. Mitra2 1Nuclear and Analytical Chemistry Section, Department of Chemistry,The University of

Burdwan, Burdwan-713409, W. B., India. 2Department of Physics, The University of Burdwan, Burdwan-713409, W. B., India.


Abstract

For the long-term storage of high-level nuclear wastes (HLW), it is required to develop

glasses with high chemical durability, thermal stability and waste solubility. In comparison with

high silica and borosilicate glasses, lead-iron phosphate glasses have the advantages of good

waste solubility and low melting temperatures so that volatile hazardous radionuclides (e.g.

Ru, Tc and Cs) can also be incorporated in the glasses. Lead–iron phosphate glasses were

proposed as the potential nuclear waste glasses, which show more durability than that of a

comparable borosilicate waste glass. In the present works simulated glass (LIP) composition

as that of the waste are selected and melted from batch oxides. Finally these glasses after

setting proper melting conditions are subjected to leaching studies under Soxhlet condition at

different medium. The melting point of the LIP4 melted with PbO as source was found to be

comparatively lower (~750°C) than in case of those melted with Pb3O4 (> 900°C). The pH

increase of the leachate solution can be distinguished and correlated to the schematic

phosphate network. At the beginning the P–O–M (M= Pb, Sr, Ce, Ba) bonds could be

preferentially corroded with a release of phosphate groups in the leaching solution contributing

to make up a drop in pH. Later on, the acidic medium could involve a corrosion enhancement

with partial hydrolysis of P–O–P band P–O–Pb bonds. As the glass is quenched from the melt,

the Fe-O-P-O-Pb network formed with voids that can be occupied by waste ions such as U4+.

The leaching rate of the LIP glasses (both with and without U) containing ceria are lower than

without ceria. This is due to having higher coordination number linked with oxygen in the

phosphate network. Hence the durability of the LIP glasses may be increased with the addition

of CeO2.



57

AWC-139

ANTIMONY SORPTION PROPERTIES OF CHITOSAN – NANO TIO2 COMPOSITE

BEADS

Padala Abdul Nishad, Anupkumar Bhaskarapillai, Sankaralingam Velmurugan#


Kalpakkam, Kancheepuram, Tamil Nadu – 603102


Abstract

Routine decontamination campaigns of nuclear reactors are generally effective in

removing various radionuclides such as cobalt, caesium, etc., and bring down the radiation

field. However, during some of the decontamination campaigns, the radiation field at some

surfaces were seen to have actually gone up. This was found to be due to lack of removal of

antimony isotopes by the regular ion exchange resins used, which subsequently deposited

over out of core surfaces leading to increased radiation field on those surfaces. Thus there

exists a need for efficient antimony removal system. We have synthesised nano titania

impregnated - epichlorohydrin crosslinked chitosan beads, which were found to have high

sorption capacity for antimony. The beads, which were synthesised in formats suitable for

large scale (column mode) applications, were shown to be effective sorbent of antimony in

both +3 and +5 oxidation states. The sorbent exhibited complete removal of antimony from its

aqueous solutions of concentration ranging from 150 ppb to 120 ppm. In order to understand

the sorption mechanism and to fine tune the bead composition, the effect of crosslinker

concentration used during the synthesis on the swelling and sorption properties of the beads

was investigated in detail. The variation effected significant changes in physical parameters

such as bead diameter, swelling ratio, equilibrium water content and true wet density. Sorption

capacity, unlike with regular resins, was found to increase with increase in crosslinker amount.

The antimony sorption capacity of the crosslinked beads prepared by crosslinking 0.3 g

uncrosslinked beads with 6.4 mmol epichlorohydrin (crosslinker) was 493 µmol/g. Non-

crosslinked beads showed a capacity of 75 µmol/g, while the crosslinked beads made with

the least amount of crosslinker (0.64 mmol per 0.3 g beads) showed a capacity of 133 µmol/g.

These results indicate the possible involvement of the crosslinker in the sorption.



58

AWC-141

HEAVY METALS-BIOREMEDIATION BY HIGHLY RADIORESISTANT

DEINOCOCCUS RADIODURANS BIOFILM PROSPECTIVE USE IN NUCLEAR

REACTOR DECONTAMINATION

Sudhir K. Shukla, T. Subba Rao#

Biofouling & Biofilm Processes Section, Water and Steam Chemistry Division,

BARC facilities, Kalpakkam, 603 102 India,


Abstract

Over the past few decades, rapid growth of chemical industries has enhanced the

heavy metal contamination in water, thereby raising environmental concerns. In the nuclear

power industry, decontamination procedure also generates radioactive heavy metal containing

wastes. Radio-resistant Deinococcus radiodurans R1 is reported to be a potential candidate

for the treatment of low active waste material. To use any bacterium for bioremediation

purpose, knowledge about its biofilm production characteristics is a prerequisite. This is

because biofilm-mediated bioremediation processes are more efficient as compared to

processes mediated by their planktonic counterparts. However, so far there are no reports on

the biofilm producing capability of D. radiodurans. We observed that tagging of D. radiodurans

by a plasmid harbouring gfp and kanR conferred significant biofilm producing property to the

bacterium. Chemical analysis of biofilm matrix components produced by D. radiodurans

showed that the matrix consists primarily of proteins and carbohydrates with small amount of

extracellular DNA (eDNA). Further, we studied the effect of Ca2+ on D. radiodurans biofilm

formation and it was observed that D. radiodurans biofilm formation was enhanced at higher

concentrations of Ca2+. We investigated the capability of D. radiodurans biofilm to remove the

heavy metals Co and Ni from synthetic waste streams. Results showed that Ca2+ enhanced

the bioremediation of both heavy metals (Co, Ni) by D. radiodurans biofilms in a highly

significant manner. In the presence of 50 mM Ca2+ 35% Co removal and 25% Ni removal was

observed, when compared to biofilm grown in the absence of Ca2+, which showed mere 7%

Co and 3% Ni removal, respectively. The results showed that the presence of Ca2+ significantly

enhanced exopolysaccharide and eDNA (both negatively charged) production in the biofilm

matrix. This indicated adsorption could be the major mechanism behind enhanced biofilm

mediated removal of heavy metals. The study signifies the potential use of D. radiodurans

biofilms, which can tolerate >20 kGy in nuclear reactor decontamination process for the

removal of active heavy metals.



59

AWC-142

OPERATING CONDITIONS INFLUENCE CORROSION OF CARBON STEEL IN A

FRESHWATER DISTRIBUTION SYSTEM

T. Subba Rao

Biofouling & Biofilm Processes Section, Water & Steam Chemistry Division,

BARC Facilities, Kalpakkam, 603 102 India


Abstract

The influence of operating conditions (flow and no flow situations) on the corrosion of

carbon steel(CS) were simulated and investigated. Conventional microbial culture methods

and molecular tools were used to characterize the biofilm and corrosion causing bacteria.

Denaturing gradient gel electrophoresis showed significant diversity and variation in the

bacterial community. Raman spectroscopy was used to characterize the corrosion deposits,

the following iron oxide phases were identified; lepidocrocite, goethite, hematite and

magnetite. Transformation of two iron oxides hematite and magnetite vice versa was noticed

in the experimental system. In conclusion a plausible CS corrosion control method was

described.



60

AWC-143

ISOLATION AND CHARACTERIZATION OF THE MICROBIAL COMMUNITY

OF A FRESHWATER DISTRIBUTION SYSTEM

P. Balamurugan1, T. Subba Rao#


BARC Facilities, Kalpakkam, 603 102 India 1Dept of Biotechnology, Pondicherry University, Puducherry, India


Abstract

This investigation provides generic information on culturable and non-culturable

microbial community of a freshwater distribution system. Culture based and culture

independent (16S rRNA gene sequencing) techniques were used to identify the resident

microbial community of the system. Selective isolation of the fouling bacteria such as biofilm

formers and corrosion causing bacteria was also attempted. Denaturing gradient gel

electrophoresis (DGGE) was carried out and the bands were sequenced to obtain the diversity

of the total bacterial types. Pseudomonas aeruginosa was predominantly observed in most of

the samples. A variety of bacteria, related to groups such as Cyanobacteria, Proteobacteria,

Actinobacteria, Bacteroidetes and Firmicutes were identified. The study highlights the

relevance of the observed microbial diversity with respect to material deterioration in a

freshwater distribution system, which can aid in designing effective control methods.



61

AWC-144

MICROFOULING ASSESSMENT AND ITS CONTROL IN A HEAVY WATER

PRODUCTION UNIT

Rajesh Kumar, T. Subba Rao#


BARC Facilities, Kalpakkam, 603 102 India


Abstract

The water treatment plant (WTP) of a heavy water production unit was extensively

fouled by microorganisms. On-site investigations showed severe algal and bacterial growth in

the various units of WTP and very dense microbial fouling in the vacuum degasser (VD) unit.

Digital and microscopic images showed that the microfouling problem was primarily due to a

slime bacterium and a fungus. Microbiological analysis showed a bacterial count of ~105 cfu

ml-1 in the various sections of WTP. The slime/biofilm scrapings had very high bacterial

population (>109 cfu cm-2). High organic carbon values in the system (5.0 to 19.5 ppm) had

supported microbial growth in WTP and augmented resin fouling. Chlorination was inadequate

in controlling microfouling, consequently chlorine dioxide was tested and found to be a better

biocide. A 2.0% sodium omadine solution had completely inhibited the fouling fungus.



62

AWC-145

CORROSION OF ALLOY D9 IN LIQUID SODIUM

R. Sudha1#, K. Chandran1, P. Muralidaran2 and S. Anthonysamy1 1Chemistry Group, 2 Reactor Operations and Maintenance Group,

Indira Gandhi Centre for Atomic Research

Kalpakkam 603 102, Tamil Nadu, India


Abstract

Alloy D9 (15Cr-15Ni-Mo-Ti-Si) is chosen as clad and wrapper material for 500 MWe

Prototype Fast Breeder Reactor (PFBR) at Kalpakkam. The successful operation of the

reactor depends on the compatibility of the core structural materials such as clad and wrapper

which are subject to high neutron irradiation and in contact with high temperature liquid

sodium. The chemical compatibility of sodium with the core structural materials is generally

good when the sodium is in the pure state. One of the major criteria for selection of clad and

wrapper materials is corrosion in liquid sodium environment. The corrosion of alloy D9 in

presence of sodium was studied at different temperatures (773, 798, 823 and 873 K) for

various duration of time ranging from 1000 to 3000 h in a well characterized sodium loop. The

observed corrosion data such as weight loss, depleted layer formation, changes in

microstructure of the alloy D9 specimens are compared with the literature data available on

sodium corrosion in static condition. The corrosion rates in dynamic and static sodium are

comparable in the measured temperatures as the purity of sodium with respect of oxygen

concentration is comparable. The corrosion rate is faster at higher temperature and for longer

duration of exposure to liquid sodium. Loss of thickness of material at 873 K is less than 5 µm

per year. Exposure to sodium causes selective dissolution of alloying elements such as nickel

and chromium. The metal losses, thickness of corroded layers and changes in chemical

composition were only marginal at a maximum temperature of 873 K. Hence alloy D9 is a

good choice for clad and wrapper tube material.



63

AWC-146

THREE DECADES OF EXPERIENCE WITH COOLING WATER SYSTEM OF A

FAST REACTOR

A.Suriyanarayanan# and B.S.Panigrahi

Reactor Chemistry Section, Reactor Operation & Maintenance Group,

Fast Breeder Test Reactor, Indira Gandhi Centre for Atomic Research,

Kalpakkam - 603102 (TN), India


Abstract

The cooling water system constitutes the terminal heat exchange system for the fast

breeder test reactor (FBTR) which is a sodium cooled fast reactor of 40 MWt capacity. It

transfers the residual heat to atmosphere through a cooling tower. Cooling water system of

FBTR comprises two sub-systems namely condenser cooling water system and service water

system. Condenser cooling water is circulated through main condenser, dump condenser,

condensate cooler, generator air cooler and turbine oil cooler. Service water system removes

heat from several heat exchangers of auxiliary systems like air compressor, cold trap cooling,

nitrogen plant, Biological Shield Cooling (BSC), Diesel Generator (DG) and steam-water

system sample coolers. The cooling water system consists of an open recirculating type with

an induced draft cooling tower as the ultimate heat sink. Initially, Palar river water was used

as the cooling medium. At present, due to scarcity of river water, sub soil water and output

from Nuclear Desalination Demonstration Plant (NDDP) are also used as cooling water. The

material of construction of pipe line is carbon steel and the heat exchanger tube and other

equipment materials are copper, admiralty brass, aluminium brass, bronze, Cu-Ni and carbon

steel.

The construction of the cooling water system of FBTR was completed in 1980. Since then the

sub-systems were commissioned one by one. Whenever a sub system was commissioned, it

generated a lot of impurities which affected the existing treatment programme. Sodium hexa

meta phosphate treatment, Langelier Index monitoring, chlorination, global and target

dispersant addition at high heat flux heat exchanger , chemical cleaning of corroded

pipelines, corrosion monitoring , side stream filtration, addition of phosphonate-based

corrosion inhibitor, broad spectrum biocide and specific biocide for iron oxidising bacteria

are some of the phases of the cooling water treatment programme. At present, corrosion rates

are generally less than 3 mpy for carbon steel and less than 0.5 mpy for brass.

This paper details the challenges faced and remedial measures implemented in the cooling

water system of FBTR for better performance and increased availability.



64

AWC-156

WATER TREATMENT WITH CHLORINE: INFLUENCE OF SOURCE WATER

CHARACTERISTICS ON CHLORINATION & CBPS FORMATION

R K Padhia, S Subramaniana, K K Satpathya#

a Environment & Safety Division, RSEG /EIRSG, Indira Gandhi Centre for Atomic Research,

Kalpakkam, Tamil Nadu- 603 102, India.


Abstract

Chlorine is cheap, reliable and proven oxidant used worldwide for drinking water

disinfection and bio-fouling control in water utilities. Formations of toxic trihalomethanes

(THMs) due to the reaction of chlorine with natural organic matter present in water have raised

concern over its use for water treatment. Ambient source water characteristics and

operational parameters dictate the THMs load in the chlorinated water. To evaluate the effect

of change in water quality parameters on chlorination and chlorination byproducts (CBPs)

formation, laboratory chlorination experiments were carried out for two source water viz. Palar

River (PR), Open reservoir (OR). Chlorine demand (CD) and total trihalomethanes formation

potential (TTHMF) were measured for different contact time. CD and TTHMF were always

observed to be higher for open reservoir water. Chlorine demand value for open reservoir

ranged from 1.48 to 2.43 mg/L and that of Palar water ranged from 1.01 to 1.76 mg/L. TTHMF

potential (TTHMFP) of Open reservoir ranged between 61-98 µg/L which was relatively higher

compared to that for Palar (38-94 µg/L). Water quality descriptors such as temperature, pH,

Chlorophyll and dissolved oxygen of subsoil Palar River water was found to undergo

substantial alteration upon open storage in the open reservoir. Dissolved organic content

(DOC) of the two water sources studied i.e Palar river subsoil water (PR) and open reservoir

water (OR) varied from 0.41 to 0.95 mg/L and 0.93 to 2.53 mg/L respectively. Presence of

bromide in these water sources (0.15 – 0.26 mg/L in PR and 0.17 -0.65 mg/L in OR) have

resulted significant brominated THMs. The formation of more amounts of brominated THMs

lead to enhanced toxicity load in the chlorinated water.

Key words: Chlorination, Chlorination byproduct, Chlorine demand, Dissolved organic content

Trihalomethanes



65

AWC-158

ENTRAINMENT AND IMPINGEMENT OF AQUATIC FAUNA AT COOLING

WATER SYSTEM OF MADRAS ATOMIC POWER STATION (MAPS)

S. Barath Kumar*, N. P. I. Das and K.K. Satpathy

Environmental and Safety Division, Radiological Safety & Environmental Group, Electronics

Instrumentation & Radiological Safety Group, IGCAR, Kalpakkam, Tamil Nadu, India-60310


Abstract

In order to understand the entrainment and impingement of marine fauna at the cooling

water system of Madras Atomic Power Station (MAPS), a pilot study programme for one year

(March 2013 to February 2014) period was carried out. In this regard entrapped fauna were

recorded on hourly scale at three cooling water screens of MAPS on weekly basis (76

sampling). The entrained specimens were categorized, weighed and observed for

impingement effect. The study showed that the major entrained groups of animals were

jellyfish, crab, fish and shrimp. Apart from above, a few cephalopods and sea snakes were

also observed as entrained entity. Totally 67 species of marine faunas impinged on the water

intake screens of MAPS during the study. The numerical count of the total observations during

the study period showed jellyfishes were the largest entrained group covering around 44.85%

of individual and constituting almost 94.82 % of biomass recorded during the study period and

sea nettle jelly (Chrysaora quinquecirrha) was impinged with highest frequency. The monthly

data analysis showed large scale jellyfish entrainment during March, April, August and

October. This is mostly due to the jellyfish bloom at Kalpakkam coast during this period. The

next entrained group was crab, which counts 30.37% individuals and on biomass counts for

2.93% of the total entrained fauna. A total of 16 species of crabs were observed as entrained

groups, of which Swimming crab (Charybdis lucifera), Stone crab (Menippe rumphii) species

were frequently impinged (> 63% occurrence). Both the crab species have no or low

commercial value as found from the local fisher folk. The next entrained group was fish which

accounts for 14.84 % of individual count and mere 1.67 % of biomass. Totally 33 number of

fish species were observed. The highest impinged species were pony fishes (Secutor

ruconius, Secutor insidiator, Photopectoralis bindus, Alepes kleinii and Leiognathus equulus)

(21% occurrence). These few entrained fishes are mostly very small in size and have less

commercial value. The other entrained group such as shrimps (0.31%), sea snakes (0.19 %)

and cephalopods (0.06%) were rarely observed and negligible in biomass count, comprising

less than 1% of entrained biomass. The monthly study trend showed crab impingement

declines from September to February. In case of fish, the highest impingement was observed

during the month of December, on night and on full moon day. In the total faunal highest

impingements occurred at night time, full moon day and low tide compared to the day time,

new moon day and high tide. The present data when compared with the impingement data

from other coastal power plants, shows that the impinged fish biomass at MAPS cooling water

system is much less than the other temperate and tropical power plants.



66

AWC-159

SURFACE AND ELECTROCHEMICAL CHARACTERIZATION OF NANO ZINC

FERRITE COATING ON CARBON STEEL

Sumathi Suresh, S. Rangarajan# and S. Velmurugan

Water and Steam Chemistry Division

BARCF, Kalpakkam, INDIA


Abstract

The structural materials in the nuclear power reactors are mainly iron and nickel based

alloys. Operation of these nuclear reactors at high temperatures and high pressures for a

longer duration leads to the formation of various oxides due to the corrosion of the structural

materials and the nature of these oxides depend on the chemical environment prevailed. Since

the corrosion process is usually electrochemical in nature, the interface formed between the

alloys and the oxides play a crucial role in deciding the overall corrosion resistance of the

structural materials. Therefore, modifying these oxides to nano size would improve the

adherence and protectiveness of the interfacial film. In this context, the chemical synthesis of

zinc ferrite (ZnFe2O4) was carried out by precipitation method using zinc sulphate and iron

ammonium sulphate. The synthesized ferrite powder was confirmed by Raman Spectroscopy.

X-Ray Diffraction studies showed that the intensity and the ‘d’ values of the entire observed

diffraction peaks perfectly match with the single-crystalline cubic spinel form of zinc ferrite

having lattice constant a= 8.436 Å. The ferrite targets were prepared (10 mm diameter pellet

with a calculated density of 4.22 gm/cm3) using synthesized ZnFe2O4 powder by sintering at

1000°C for 24 hours. Thin film of ZnFe2O4 was deposited on Carbon Steel specimens using

pulsed laser deposition technique. Characterization of the deposited ferrite was carried out

using Laser Raman, X-Ray Diffraction, X-ray Photoelectron Spectroscopy and Secondary

Electron Microscopy. Raman data of the coated ZnFe2O4 matched with the standard ZnFe2O4

oxide. X-ray diffraction pattern indicated that the sample was in single phase with an average

grain size 30 nm. XPS data clearly indicated the formation of the ZnFe2O4. Scanning electron

microscopy and atomic force microscopy techniques were used to analyze the film surface

morphology. The mechanism of corrosion resistance / improvement in the deposited layer was

studied by electrochemical techniques and the results are presented in detail in this paper.


67

AWC-163

EVALUATION OF CORROSION INHIBITORS FOR HIGH TEMPERATURE

DECONTAMINATION APPLICATIONS

V. S. Sathyaseelan, A. L. Rufus and S. Velmurugan#


Kalpakkam, Tamilnadu – 603 102, INDIA

#Corresponding email: [email protected]

Abstract

Normally, chemical decontamination of coolant systems of nuclear power reactors is

carried out at temperatures less than 90 °C. At these temperatures, though magnetite

dissolves effectively, the rate of dissolution of chromium and nickel containing oxides formed

over stainless steel and other non-carbon steel coolant system surfaces is not that

appreciable. A high temperature dissolution process using 5 mM NTA at 160 °C developed

earlier by us was very effective in dissolving the oxides such as ferrites and chromites.

However, the corrosion of structural materials such as carbon steel and stainless steel also

increased beyond the acceptable limits at elevated temperatures. Hence, the control of base

metal corrosion during the high temperature decontamination process is very important. In

view of this, it was felt essential to investigate and develop a suitable inhibitor to reduce the

corrosion that can take place on coolant structural material surfaces during the high

temperature decontamination applications with weak organic acids. Three commercial

inhibitors viz., Philmplus 5K655, Prosel PC 2116 and Ferroqest were evaluated at ambient

and at160 °C temperature in NTA formulation. Preliminary evaluation of these corrosion

inhibitors carried out using electrochemical techniques showed maximum corrosion inhibition

efficiency for Philmplus. Hence, it was used for high temperature applications. A concentration

of 500 ppm was found to be optimum at 160 oC and at this concentration it showed an inhibition

efficiency of 62% for carbon steel. High temperature dissolution of oxides such as Fe3O4 and

NiFe2O4, which are relevant to nuclear reactors, was also carried out and the rate of dissolution

observed was less in the presence of Philmplus. Studies were also carried out to evaluate

hydrazine as a corrosion inhibitor for high temperature applications. The results revealed that

for carbon steel inhibition efficiency of hydrazine is comparable to that of Philmplus, while for

stainless steel hydrazine is a better choice.



68

AWC-171

DEVELOPMENT OF LEACHING METHOD FOR THE ANALYSIS OF

PALLADIUM CATALYST USED IN THE MODERATOR COVER GAS CIRCUIT

OF MAPS BY ICP-OES

S. Vijayalakshmi# and S. Annapoorani,

Materials Chemistry Division, IGCAR, Kalpakkam

#Corresponding author: [email protected] Abstract

The radiolysis of heavy water, which is used as Moderator in PHWRs results in the

formation of D2 and O2 which strips into the helium cover gas. Considering the safety aspect,

there is a technical specification limit for the concentration of D2 in moderator cover gas and

the upper limit is 4%v/v. To control the D2 concentration within this limit during reactor

operation, part of the cover gas flow is passed through the recombination units in the

moderator cover gas circuit. There are two recombination units and each contains pellets of

Palladium coated alumina as catalyst in which the recombination of D2 and O2 gas takes place.

To improve the efficiency of the recombination units, catalyst containing 0.5% Pd is preferred

over 0.2% Pd and therefore the same was taken up for use in Madras Atomic Power Station

(MAPS). Analysis of palladium catalyst was required towards the quality control purpose. The

catalyst contains palladium as coating over the alumina pellets. Therefore, in this study,

leaching procedure was standardized for the complete removal of palladium and the leached

solutions were analyzed by ICP-OES for the determination of palladium.

Experimental: Complete dissolution of sample requires fusion. Fusion with 100mg of sample

pieces was found to result in the poor precision of around 40%. Considering the difficulty of

powdering the sample to get better precision in fusion, leaching procedure was tried out for

analysis. 0.5gm of sample was heated with aquaregia till the disappearance of black colour

on the alumina balls. The solution was made upto known volume and appropriately diluted for

analysis. The complete removal was also checked by repeating the leaching with already

leached sample. Concentration calibration using 340.458nm line was employed for the

analysis. Both samples (sample containing 0.2% Pd and sample containing 0.5% Pd) were

analyzed in duplicate and the results were found to agree well with the expected value.

Conclusion: A simple and convenient leaching procedure was standardized and

recommended for the analysis of palladium catalyst and it was also applied to the samples

from MAPS.

Acknowledgement: Authors would like to acknowledge Chemistry Control Section of MAPS

for providing catalyst sample for standardizing the method and Dr. K. Sankaran, Head,

Analytical Chemistry and Spectroscopy Section, MCD, CG for his support in carrying out the

analysis.



69

AWC-172

DISSOLUTION OF COBALT METAL POWDER

V.S. Sathyaseelan, A. L. Rufus and S. Velmurugan#

Water and Steam Chemistry Division, Bhabha Atomic Research Centre Facilities

Kalpakkam (TN) – 603 102, INDIA


Abstract

During the transfer of Self Powered Neutron Detectors (SPNDs), from the core of the

nuclear reactor to fuel storage bay, there is every possibility of cobalt powder spillage. In order

to decontaminate the surfaces during such occasions, some studies were carried out to

dissolve cobalt powder. Various formulations such as potassium permanganate, permanganic

acid, nitric acid and nitrilo triacetic acid (NTA) were investigated for their efficiency in dissolving

metallic cobalt taken in the form of powder. Investigations revealed that a two step process

involving a surface conditioning step by permanganic acid followed by dissolution of the cobalt

powder by 10mM nitric acid will efficiently decontaminate the cavity surface.



70

AWC-174

STUDIES WITH ANTI FOULING COATING ON SEAWATER INTAKE SYSTEM

SCREENS OF MAPS

N.Sankar, V.S.Santhanam, P.Umapathi, K.Hari Krishna#, D.Rajendran,

MAPS, Kalpakkam

Dr.P.S.Murthy, and Dr.V.Venugopalan,

BBPS, WSCD, Kalpakkam #Corresponding Author:

Abstract

Biofouling has been a concern for cooling water systems of coastal power plants and

the same is being experienced in Madras Atomic Power Station (MAPS). Macro fouling

organisms cause major problems for smooth operation and maintenance of the cooling water

system. The cooling water intake structures particularly the screens, which act as the barrier

for marine organisms to enter into the cooling water system, gets fouled severely in a short

period of time. Though chlorination is being done to control biofouling, it is ineffective due to

the inward flow of seawater. Severely fouled gates necessitate frequent cleaning and

maintenance which involves lifting of heavy structures, laborious manual cleaning and

maintenance. In order to find remedial measures for the said concern, studies have been taken

up for identification of simple but effective methods in controlling bio fouling. Accordingly

studies with Anti Fouling Coating (AFC) applications have been identified and field studies

were carried out to review its effectiveness in meeting the given requirement. One of the gates

was coated with Anti Fouling coating (AFC) and exposed to sea water and the bio fouling

tendency was regularly monitored. It was noted the AFC coated gate was observed to have

less bio fouling compared to the in-practice coal tar epoxy coatings. The small quantity of

fouling deposits was generally observed to be on the side opposite to the sea water current.

The area exposed to sea water currents had relatively less biogrowth. The dislodgement or

removal of bio growth could be achieved by gentle pressure or scrapping thus demonstrating

its effectiveness in controlling the bio fouling. Studies are also in progress to with Foul release

coatings (FRC) to study its effectiveness.


71

AWC-175

INFLUENCE OF GEOMETRY OF PIPE ON FLOW ACCELERATED CORROSION

- A STUDY UNDER NEUTRAL PH CONDITION P.Madasamy, M.Mukunthan, P.Chandramohan, T.V.Krishna Mohan, and S.Velmurugan#

Water and Steam Chemistry Division BARC Facilities,

Kalpakkam – 603 102 Tamilnadu, INDIA.

Andrews Sylvanusa and E.Natarajanb aAU-FRG Institute for CAD/CAM , Anna University, Chennai-25

bInstitute For Energy Studies, Anna University, Chennai-25


Abstract

The carbon steel piping material’s degradation due to flow accelerated corrosion (FAC)

is one of the problems in nuclear power plant. FAC impacts plant operation and maintenance

significantly. Wall thinning of structural materials should be predictable based on combined

hydrodynamics analyses and experimental corrosion data. Such predictive tools help to take

preventive measures before loss of material becomes a serious issue for plant operation. In

order to develop predictive tools, data on the effect of various parameters that control FAC

are required. As per existing literature, one of the important parameters that affect FAC is

piping configuration (Geometry of flow path). Hence, experiments were carried out to assess

the role played by the geometry of the piping in the FAC of carbon steel. In this study,

experiments were conducted in simulation loop under neutral pH condition while varying the

geometry parameter of bend such as bend angle and bend radius. Therefore, pipe specimen

holder 15 NB bend with 58 o, 73° as bend angle and 4D, 2D bend radius was designed and

fabricated. The experiments were carried out in order to quantify the wear rate (wall thickness

measurement was by ultrasonic method) with a single phase flow velocity (7 m/s) under

neutral pH conditions With the pipe specimen four experiments were conducted under neutral

pH condition and at 120 °C. Wall thickness mapping was carried out by ultrasonic thickness

gauge using a template before and after the experiment. High wall thickness reduction under

neutral water chemistry enables easy measurement by ultrasonic thickness gauge. It was

observed from the first two sets (2D58°, 4D58°) that the corrosion rate with 4D, 58° was 50%

less than the corrosion with 2D 58o. Subsequently, another two sets of experiments (2D 73o

and 4D 73o) was carried out in SIM loop at 7 m/s under neutral pH conditions for two months.

Thus, this method of experiments enables us to understand the geometrical influence. The

comparison of all the four set of experiments indicated that minimum corrosion rate

(1.3mm/year) was obtained with 4D 73 geometry. Further, velocity distribution, wall shear

stress in the bend geometry were mapped by Computed Fluid Dynamics (CFD) and correlated

with the corresponding measured wear rate. Good correlation was obtained between

theoretically obtained corrosion rate and the experimental value.


72

AWC-176

EVALUATION OF PLASMA COATED CARBON STEEL TO RESIST FLOW

ACCELERATED CORROSION

P.Madasamy, J. Alphonsaa, J. Ghanshyama, S. Mukherjeea, M.Mukunthan,

P.Chandramohan, T.V.KrishnaMohan, ,E.Natarajanc and S.Velmurugan#

Water and Steam Chemistry Division BARC Facilities,

Kalpakkam – 603 102 Tamilnadu, INDIA. aInstitute for Plasma Research, Ahmedabad

cInstitute For Energy Studies, Anna University, Chennai-25.


Abstract

Coatings have historically been developed to provide protection against corrosion and

erosion that protects the material from chemical and physical interaction with its environment.

Corrosion and wear problems are still of great relevance in a wide range of industrial

applications and products as they result in the degradation and eventual failure of components

and systems both in the processing, manufacturing and power industries. Various

technologies can be used to deposit the appropriate surface protective agents that can resist

deterioration under specific conditions. They are usually distinguished by coating thickness as

it depends on method of coating. Diffusion based coatings by plasma nitriding have recently

been used for improving wear and corrosion resistance properties.

A collaborative study on plasma nitriding was initiated with FCIPT, a division of Institute of

Plasma Research.This is one of the method to control the wall thickness reduction of carbon

steel feeder pipe and the influence of FAC in PHWR. In order to control the influence of Flow

Accelerated Corrosion on feeder pipe of PHWR reactor, as a remedy, coating by plasma

nitriding process was carried out inside the pipe. The plasma coating is by nitrogen/hydrogen

mixture plasma through diffusion process and thickness of coating of upto 300 µm was

possible. The coating can withstand a temperature up to 500 °C. The limitation of this process

is that it cannot nitride pipes with inside diameter less than 5 mm. Two samples of 15 mm NB

Sch 80 straight pipe length of 10 cm pipe module section were plasma nitrided at FCIPT, IPR

for optimization of the process parameters. The wall thickness of the sample was measured

axially and circumferentially by Ultrasonic thickness gauge with specific marking with

templates before carrying out plasma nitriding process. During plasma nitriding, the

temperature was maintained at 520 oC for 24 hours. Plasma nitriding process was done using

a pulsed DC power supply. We were able to get the required temperature and the

results were as per the requirement. There was increase in hardness to 310 HV0.1 from

100HV0.1 at the outer as well as the inner surface with a case depth of more than 250 microns

in the inner surface and 650 microns on the outer surface. The samples after coating were

checked for thickness variation by Raman spectroscopy as wells as microscopy, and it was

found that the coating was uniform and coating consisted of iron nitrides only. The bend

specimen optimization of coating parameter is in progress at FCIPT/ Institute of Plasma

Research, Gandhinagar.

For functional test to check the corrosion resistance, a specimen holder was designed

and fabricated for the treated specimen such that it can withstand a velocity of 7 m/s. The

holder was mounted in SIM loop in the heater outlet. The SIM loop was maintained at 120 °C

and 7 m/s for about 30 days with less than 20 ppb dissolved oxygen condition. The experiment

is in progress in SIM loop in order to check resistance to FAC under neutral pH condition.



73

AWC-177

PREPARATION AND DISSOLUTION OF URANIUM DIBUTYL PHOSPHATE

(UDBP)

M.K.Dhanesh*, A.L.Rufus and S.Velmurugan#



*Department of Chemistry, University of Calicut, Calicut, INDIA


Abstract

A sticky coating of Uranium Dibutyl Phosphate (U-DBP) was found to be formed on

the surfaces of nuclear fuel reprocessing facilities and on the surfaces of reprocessed waste

storage tanks. This poses both radiation exposure and criticality hazard. Hence, it is required

to periodically dissolve U-DBP deposits. In this connection, an attempt was made to synthesis

U-DBP from U3O8 and to evolve a suitable chemical formulation for its dissolution. The U-DBP

complex synthesised was yellow coloured sticky deposit.

For the dissolution studies, various formulations such as EDTA, disodium-EDTA and

sodium carbonate were considered. From the literature it was seen that uranium deposits

dissolve effectively in oxidising medium. Hence, dissolution studies were carried out in above

formulations in the presence and absence of hydrogen peroxide, which is a well known

oxidising agent. From the experimental results it was seen that of all the formulations used,

sodium carbonate was found to be very efficient. In the presence of peroxide, the rate of

dissolution was found to increase. Investigations were carried out to optimise the

concentration of sodium carbonate, peroxide and also the temperature of dissolution.


74

AWC-178

STUDIES ON GADOLINIUM PRECIPITATION IN MODERATOR SYSTEM OF

NUCLEAR REACTOR

Akhilesh C Joshi, Puspalata Rajesh, A.L.Rufus and S.Velmurugan#

Water & Steam Chemistry Division

BARC Facilities, Kalpakkam 603 102, India


Abstract

Gadolinium is used in the moderator system of many Pressurised Heavy Water

Reactors (PHWRs) for start-up, shutdown and reactivity control during operation. It is very

much essential to maintain gadolinium concentration in the system as desired. It has been

reported that gadolinium gets precipitated in as oxalate in carbonated water under the

influence of -radiation. Hence, studies were carried out to investigate the effect of dose,

presence of other metal ions and metal surfaces on the precipitation of gadolinium. The results

showed that the amount of carboxylic acids viz., formic acid and oxalic acid, formed due to

radiolysis is dependent on the dose. and that the curve passes though a maxima. Gadolinium

is added in higher concentration in Advanced Heavy Water Reactor. So, experiments with

high concentration of gadolinium were also carried out. Ultra pure water saturated with high

purity CO2 containing gadolinium and desired ion/surface was irradiated with γ-radiation from

60Co source at 25oC to doses ranging from 2.5-16.6 Mrad. . At lower doses, formation of

carboxylic acids takes place but as the dose increases, decomposition of these acids starts

and hence the concentration Vs dose passes through a maximum. It was found that

precipitation of gadolinium as oxalate occurred at lower doses. At higher doses, it was seen

that pH of the solution decreases and hence solubility of gadolinium oxalate increases. It was

also observed that the amount of gadolinium precipitated varied linearly with the initial

concentration of gadolinium varying from 2 ppm to 20 ppm. While for gadolinium concentration

from 20 ppm to 400 ppm, gadolinium in particulate form was observed. The amount of

carboxylic acids formed depends on the nature of cations present in solution. It was found that

the amount of oxalic acid formed in the case of gadolinium was more than that formed in the

case of sodium. Presence of metal oxides such as ZrO2 formed over zircoloy surfaces was

found to enhance the precipitation of gadolinium. This was confirmed from the stronger XPS

peak of gadolinium in presence of ZrO2 compared to that in absence of ZrO2 showed the

enhanced precipitation of gadolinium in presence of ZrO2.Further, the precipitation of

gadolinium was also found to be influenced in the presence of metal surfaces such as zircoloy.



75

AWC-179

OBSERVATIONS ON THE REMOVAL OF GADOLINIUM FROM THE

MODERATOR SYSTEM OF PRESSURISED HEAVY WATER REACTOR (PHWR)

AND ADVANCED HEAVY WATER REACTOR (AHWR)

V. Praveena*, Padma S. Kumar, A.L. Rufus and S. Velmurugan#



*Department of Chemistry, University of Calicut, Calicut, INDIA


Abstract

Investigation on ion exchange removal of gadolinium taken as gadolinium nitrate,

which is used as neutron poison in the moderator system of Pressurised Heavy Water Reactor

(PHWR) and proposed to be used in Advanced Heavy Water Reactor (AHWR) was carried

out. Mixed bed operation consisting of (a) strong acid cation resin (SAC) and strong base

anion resin (SBA) and (b) strong acid action resin and acrylic acid based nitrate loaded weak

base anion resin were employed for the removal gadolinium from its aqueous solution at pH

5. In the former case, the outlet of the mixed bed was highly alkaline, which resulted in

precipitation of gadolinium hydroxide. In the latter case, the pH of the system never crossed 6

and gadolinium was effectively picked up on the resin without getting precipitated.

Series operation consisting for strong acid cation resin followed by mixed bed column

consisting of strong acid cation resin and strong base anion resin/acrylic acid based weak

base anion resin was also investigated. In the first case where strong base anion resin was

used, there was precipitation in the system owing to the increase in pH while in the case where

weak base anion resin was used there was no problem of precipitation and gadolinium

removed effectively and the pH was around 6.


76

AWC-180

CHEMISTRY MANAGEMENT OF GENERATOR STATOR WATER SYSTEM

N. Sankar, V.S. Santhanam, S.R. Ayyar, P. Umapathi, P. Jeena, K. Hari Krishna,

D.Rajendran

Madras Atomic Power Station, Kalpakkam


Abstract

Chemistry management of water cooled turbine generators with hollow copper

conductors is very essential to avoid possible re-deposition of released copper oxides on

stator windings, which otherwise may cause flow restrictions by partial plugging of copper

hollow conductors and impair cooling. The phenomenon which is of more concern is not strictly

of corrosion failure, but the consequences caused by the re-deposition of copper oxides that

were formed by reaction of copper with oxygen. There were also some Operating experiences

(OE) related to Copper oxide fouling in the system resulting shut down/off-line of plants.

In Madras Atomic Power Station (MAPS), the turbine generator stator windings are of Copper

material and cooled by demineralized water passing through the hollow conductors. The

heated water from the stator is cooled by process water. A part of the stator water is

continuously passed through a mixed bed polisher to remove any soluble ionic contaminants

to maintain the purity of system water and also maintain copper content as low as possible to

avoid possible re-deposition of released copper oxides on stator windings. The chemistry

regime employed is neutral water with dissolved oxygen content between 1000-2000ppb.

Chemistry management of Stator water system was reviewed to know its effectiveness.

Detailed chemical analyses of the spent resins from the polishing unit were carried out in

various campaigns which indicated only part exhaustion of the polishing unit resins and

reasonably low levels of copper entrapment in the resins, thus highlighting the effectiveness

of the in-practice chemistry regime.



77

AWC-181

STUDIES WITH SOLID CHLORINE CHEMICAL FOR CHLORINATION OF SEA

WATER SYSTEMS

N.Sankar, P. Kumaraswamy, V.S. Santhanam, P. Jeena, K. Hari Krishna#, D. Rajendran,

Madras Atomic Power Station, Kalpakkam


Abstract

Chlorination is one of the conventional methods to control biofouling of condenser

cooling water systems using either river water, reservoir water or sea water. However, there

are many safety concerns associated with handling, storage and application of gaseous

chlorine. Studies were carried out with suitable alternativee chlorine chemical compounds

which do not involve majority of these concerns but meet the functional requirement of gas

chlorine. Trichloroisocyanuric Acid (TCCA) is one of the suitable alternatives to Gas chlorine.

TCCA is a chlorine stabilized compound, stabilized with Cyanuric acid, thus similar to Gas

Chlorine in its functions except that it is available in solid form. Release of chlorine is a gradual

process in TCCA unlike Gaseous chlorine. Field studies with TCCA indicated gradual and

near uniform release rate of chlorine, for longer duration with the requisite free residual

chlorine levels (FRC). Thus, use of TCCA could be considered as a suitable alternative for

gas chlorine for regular chlorination requirements.



78

AWC-182

CORROSION RATE OF CARBON STEEL IN NEUTRON SHIELD TANK WATER

R. Ramakrishnan#, N. Rathinasamy and K. V. Ravi

PRPD, Kalpakkam

#Corresponding Author: [email protected] Abstract

Neutron shield tank (NST) is an open tank of 12.5 meters height and 12 meters dia

constructed around the reactor and filled water to provide sufficient shielding from the neutron

radiation, to absorb the heat from the Containment Pressure suppression system during LOCA

and to act as heat sink. NST is made of IS2062 carbon steel and it contains the stainless steel

tanks, CS support structures, forged carbon steel gas cylinders, steel containment and its

supports and emergency cooling down system condensers made of ASTM 350 gade LF2

carbon steel .All the equipments/systems located inside NST are painted with epoxy paint.

NST is filled up 12meters ie with1200 m3 of water.

The water chemistry parameters and microbiological parameters and corrosion rate of

carbon steel materials in NST water at various water chemistry and various depths are

discussed in the paper



79

AWC-183

OPTIMUM THICKNESS EVALUATION OF ZRO2 COATING ON TYPE 304L

STAINLESS STEEL FOR CORROSION PROTECTION

Nidhi Garg, Santanu Bera, V. S. Tripathia, Vijay Karkib and S. Velmurugan Water and Steam Chemistry Division,

Bhabha Atomic Research Centre Facilities, Kalpakkam aRadiation and Photochemistry Division, BARC, Mumbai

bFuel Chemistry Division, BARC, Mumbai .


Abstract

Nano-crystalline ZrO2 coatings of different thicknesses have been grown on pre-

oxidized stainless steel (SS) surface by hydrothermal method in an autoclave. Thickness of

the coating has been enhanced by repeating the deposition process several times using same

precursor concentration. Several cycles of the deposition process lead to the increase of the

coating thickness from 200 nm to ~1 m after the fourth cycle. The samples after different

cycles of the coating have been extensively characterized by SEM-EDS technique to find the

surface topography, coating thickness and composition. Corrosion resistance properties of the

plain SS, pre-oxidized SS and all the ZrO2 coated samples were studied by potentiodynamic

polarization technique and electrochemical impedance spectroscopy (EIS). Corrosion current

densities (Icorr/cm2) of the coated samples are found to reduce significantly with the increase

in thickness. After a certain critical thickness, the corrosion current density observed to attain

a stable value. The coating was found to be continuous but porous after the first cycle but

porosity of zirconia coating have been reduced drastically after the second cycle itself. EIS

analysis confirms that the zirconia coated samples show insulating, barrier like characteristics

in terms of high charge transfer resistance after the second cycle of zirconia deposition. The

role of pre-oxidized surface composition and the interface between the pre-oxidized surface

and the coating has been discussed in details by showing the depth distribution of Zr in the

coating.



80

AWC-184

IODINE REMOVAL IN CONTAINMENT FILTERED VENTING SYSTEM DURING

NUCLEAR ACCIDENT

SubrataBera#, D. B. Nagrale, Anuj Kumar Deo, U. K. Paul, M. Prasad, A. J. Gaikwad




Abstract

Post Fukushima nuclear accident, containment filtered venting system (CFVS) is being

introduced in Indian NPP to strengthen the defense in depth safety barrier by reducing the

containment pressure and ensuring the containment of potential radio-nuclides released

during a severe accident. Radioactive iodine ( e.g. I-131, I-132, I-133, I-134, I-135 , etc.) is

one of the major contributors to radiation dose during early release phase of a severe accident.

Physical and Chemical form of iodine and iodine bearing compounds includes particulates,

elemental and organic. In the proposed design of CFVS, wet scrubbing mechanism has been

employed where in iodine will be removed through chemical reaction in highly alkaline

aqueous solution and impingement of particulates with water droplets produced in the venturi

nozzle. In this paper various regulatory aspects of CFVS system have been brought out such

as validation of CFVS system, scrubber efficiency, measurement techniques involved,

radiological impact assessment, radiation shielding requirement, etc. Analysis related to

verification of the CFVS has been carried out through the estimation of full core inventory of

iodine along with its isotopic distribution for a typical boiling water reactor.

Keywords: CFVS, wet scrubber, Radioactive Iodine


81

AWC-186

AN OPERATIONAL EXPERIENCE WITH COOLING TOWER WATER SYSTEM

IN CHILLING PLANT

Manju B Rajan#, Ankan Roy, KV Ravi

PRPD, BARC, Kalpakkam – 603102


Abstract

Cooling towers are popular in industries as a very effective evaporative cooling

technology for air conditioning. Supply of chilled water to air conditioning equipments of

various plant buildings and cooling tower water to important equipments for heat removal is

the purpose of chilling plant at PRPD. The cooling medium used is raw water available at

site. Water chemistry is maintained by make-up and blowdown. In this paper, various

observations made during plant operation and equipment maintenance are discussed.

The issues observed was scaling and algal growth affecting the heat transfer and

availability of the equipment. Corrosion related issues were observed to be less significant.

Scaling indices were calculated to predict the behavior.


82

AWC-187

CONTAINMENT BEHAVIOR DURING MOLTEN CORIUM CONCRETE

INTERACTION

Anuj Kumar Deo#, S. P. Lakshmanan, S. Bera, Balbir K. Singh, P. K. Baburajan, R. S. Rao, U. K. Paul & A. J. Gaikwad




Abstract

During a severe accident in a NPP involving core melt and vessel-failure, the molten

corium may fall in the cavity where it can react with the concrete basemat leading to the

phenomena known as Molten Corium Concrete Interaction (MCCI). Due to the decay heat of

the fission products, the un-cooled hot corium can cause ablation and decomposition of the

concrete and thus penetrate the wall of the basemat which may result in loss of containment

integrity. This may offer a potential route for release of radioactive materials to the soil and

into the environment. Concrete is mainly composed of: SiO2, CaCO3 and H2O. Decomposition

of concrete during heat-up starts with evaporation of physically bound water around 100°C.

Dehydration of chemically bound water occurs up to 550°C. Decarbonation of CaCO3 (CaCO3

=>CaO + CO2) from the cement and carbonate aggregates occurs approximately between

700°C and 900°C. Liquid phases start to form between 1100°C and 1450°C. During concrete

ablation, and corium oxidation, release of non-condensable gases (H2, CO, CO2) takes place

into the containment and these gases may cause over pressurization of the containment.

In the present work, a simplified analytical model of a typical BWR containment has been

developed for ASTEC code to study the effect of MCCI on containment. The mass, physical

composition and condition of the corium (debris introduced in ASTEC model) have been

computed using the RELAP/SCDAP code. Rate of generation of hydrogen and non-

condensable gases are obtained using ASTEC for postulated initiating event of LOCA with

failure of ECCS.

Keywords: MCCI, Containment, ASTEC, MEDICIS, Severe Accidents


83

AWC-188

DEUTERISATION OF MIXED BED ION EXCHANGE RESIN: KINETICS STUDY

Satinath Ghosh1*, M. K. Tripathy1, Kajal Dhole1*, T. Vasudevan1,

Satyam Shukla2 and R. S. Sharma1

Research Reactor Services Division1, Reactor Operations Division2,

Bhabha Atomic Research Centre, Trombay, Mumbai-85.

*Corresponding Author: [email protected] (Kajal Dhole); [email protected] (Satinath

Ghosh)

Abstract

The process of deuterisation of a mixture of strongly acidic cationic and strongly basic

anionic resins in a mixed bed system has been investigated for kinetics measurement through

laboratory scale experiment. The up-flow fluidization method employing a heavy water flow

from the bottom end of the mixed bed column at a reasonably low flow rate has been amply

exploited for displacement of light water molecules inside the resin pores and adhering to resin

surface as well. The course of deuterisation has been tracked down by determination of D2O

content as a function of time and the process is found to exhibit a breakthrough type sigmoidal

kinetics. An empirical relation, involving half-life of deuterisation and some process

parameters such as flow rate, volume of light water to be replaced, could be achieved for plant

scale deuterisation of a mixed bed ion exchanger prior to use in purification unit of heavy water

process system of a nuclear reactor.




84

AWC-189

FEASIBILITY STUDY ON NANO-STRUCTURED COATINGS TO MIGATE FLOW-

ACCELERATED CORROSION OF CARBON STEEL PIPING SYSTEM

Seunghyun Kim, Jeong Won Kim and Ji Hyun Kim#

Ulsan National Institute of Science and Technology

UNIST-gil 50, Eonyang-eup, Ulju-gun, Ulsan, Republic of Korea

# email Corresponding Author: [email protected]

Abstract

To mitigate or prevent the flow-accelerated corrosion (FAC) of carbon steel pipes in

secondary system of nuclear power plants, nano-structured coatings were adopted to

supressed the dissolution of ferrous and magnetite ions. As candidates, TiO2 nano-particle

reinforced electroless nickel plating and high-velocity oxy-fuel (HVOF) sprayed Fe-based

amorhpous metallic coating (AMC) were selected and in order to evaluate their

microstructures, electrochemical properties and FAC resistance characteristics using electron

micrscopes, potentiodynamic polarization, electrochemical impedance spectrscopy and

rotating cylinder autoclave systems.

Microstructure analysis showed that TiO2 nano-structures and nano-crystalline

structures were observed in Ni-P-TiO2 and HVOF Fe-based AMC, respectively. These

structures induces the improved electrochemical properties according to high-temperature

electrochemical experiments because diffusion of aggressive impurities were suprressed. As

further work, the FAC simulation experiments using rotating cylinder autoclave system will be

carried out.

Name Country email Organization

Akhilesh C Joshi India [email protected], Bhabha Atomic Research Centre

Alphonsa Joseph India [email protected], [email protected]

Institute for Plasma Research

Amit Ravindra K India [email protected] Bhabha Atomic Research Centre

Amitava Roy India [email protected] Bhabha Atomic Research Centre

Ananthan P India [email protected] Bhabha Atomic Research Centre

Anil Pathrose India [email protected] Bhabha Atomic Research Centre

Ankan Roy India [email protected] Bhabha Atomic Research Centre

Anuj Kumar Deo India [email protected] Atomic Energy Regulatory Board

Anupkumar B India [email protected] Bhabha Atomic Research Centre

Ashwani Maheshwari India [email protected] Nuclear Power Corporation of India Limited

Babu S India - KARP, Kalpakkam

Bairwa K K India [email protected] Bhabha Atomic Research Centre

Balaji Gupta India [email protected] L&T , India

Balaji V India [email protected] Bhabha Atomic Research Centre

Barath Kumar S India [email protected] Indira Gandhi Centre for Atomic Research

Basuki Baral India Atomic Energy Regulatory Board

Biplob paul India [email protected] CWMF, Kalpakkam

Brij Mohan India [email protected] Nuclear Power Corporation of India Limited

Chandramohan P India [email protected], [email protected]

Bhabha Atomic Research Centre

Chandran T J India [email protected] Bhabha Atomic Research Centre

Chellapandi P India [email protected] Bharatiya Nabhikiya Vidyut Nigam Ltd

Cho Jae Seon Korea [email protected] FNC Tech

Christoph Stiepani Germany [email protected] AREVA GmbH,

Dash S C India [email protected] Nuclear Power Corporation of India Limited

Debasis Mal India [email protected] Bhabha Atomic Research Centre

Deepa Papachan India [email protected] Nuclear Power Corporation of India Limited

Dey G R India [email protected] Bhabha Atomic Research Centre

Dharuman S India [email protected] Bhabha Atomic Research Centre

Dipankar Nanda India [email protected] Raja Ramanna Centre for Advanced

Technology

Dineshkumar India [email protected]. BioLogic Science Instruments Pvt. Ltd.

Dong Seok Lim Korea [email protected] FNC Tech.,

Das N P I India [email protected] Indira Gandhi Centre for Atomic Research

Francis Vincent India [email protected] Bhabha Atomic Research Centre

Ganapathysubramanian India [email protected] Indira Gandhi Centre for Atomic Research

Ganesh S India [email protected] Nuclear Power Corporation of India Limited

George P J India [email protected] Bhabha Atomic Research Centre

George R.P. India [email protected] Indira Gandhi Centre for Atomic Research

Gopal Grandhi India [email protected] Atomic Energy Regulatory Board

Hari Krishna K India [email protected] Nuclear Power Corporation of India Limited

Harinath Y V India [email protected] Bhabha Atomic Research Centre

Hazra G India [email protected] Burdwan University

Hee-Sang Shim Korea [email protected] Korea Atomic Energy Research Institute

Hee-Sang Shim Korea [email protected] Korea Atomic Energy Research Institute

Helmut Nopper Germany [email protected] AREVA GmbH

Hiren Joshi M India [email protected] Bhabha Atomic Research Centre

Hur D.H. Korea [email protected] Korea Atomic Energy Research Institute

Jagatap B N India [email protected] Bhabha Atomic Research Centre











Name country email Organization

Jayasree Sriram India [email protected] Bhabha Atomic Research Centre

Jaymin Gandhi India [email protected] Adani Infra India Ltd

Jeena P India [email protected] Nuclear Power Corporation of India Limited

Kaikondan A India [email protected] Bhabha Atomic Research Centre

Kamachi mudali U India [email protected] Indira Gandhi Centre for Atomic Research

Kazushige Ishida Japan [email protected] Hitachi Ltd.

Kenji Hisamune Japan [email protected] The Japan Atomic Power Company

Keny S J India [email protected] Bhabha Atomic Research Centre

Kiran Kumar Reddy G India [email protected] Bhabha Atomic Research Centre

Koteeswaran T J India [email protected] Nuclear Power Corporation of India Limited

Krishna Mohan T V India tvkm@@igcar.gov.in Bhabha Atomic Research Centre

Lakshmanan S P India [email protected] Atomic Energy Regulatory Board

Lalu Thomas India [email protected] L&T , India

Laxmi Narayan Gupta India [email protected] Institute for Plasma research,

Madasamy P India [email protected], Bhabha Atomic Research Centre

Mahendra Prasad India [email protected] Atomic Energy Regulatory Board

Malathy Nagarajan India [email protected] Bhabha Atomic Research Centre

Manjanna J India [email protected] Rani Channamma univeristy

Manju B Rajan India [email protected] Bhabha Atomic Research Centre

Manju Gupta India [email protected] AREVA GmbH

Maruthu Pandiya Raja S India [email protected] Bhabha Atomic Research Centre

Mathur P K India [email protected] Retd. Bhabha Atomic Research Centre

Meng-Jen Chen Taiwan [email protected] Taiwan Power Company

Mishra A. K India [email protected] CWMF, Kalpakkam

Mishra H India [email protected] Bhabha Atomic Research Centre

Muktibodh U C India Nuclear Power Corporation of India Limited

Mohanty A K India [email protected] Indira Gandhi Centre for Atomic Research

Mukunthan M India [email protected] Bhabha Atomic Research Centre

Murugan M R India [email protected] Bhabha Atomic Research Centre

Muthukumaran N India [email protected] NDDP, Kalpakkam

N. Jayaraman India [email protected] Bhabha Atomic Research Centre

Narasimhan S V India [email protected] Retd. Bhabha Atomic Research Centre

Natarajan E India [email protected] Anna University

Nidhi Garg, India [email protected] Bhabha Atomic Research Centre

Nilesh Patel India [email protected] Adani Infra India Ltd

Osamu Shibasaki Japan [email protected] Toshiba Corporation

Padala Abdul Nishad India [email protected] Bhabha Atomic Research Centre

Padhi R K India [email protected] Indira Gandhi Centre for Atomic Research

Padma S.Kumar India [email protected] Bhabha Atomic Research Centre

Pal P K India [email protected] Nuclear Power Corporation of India Limited

Panigrahi B S India [email protected] Indira Gandhi Centre for Atomic Research

Pankaj Wani India Nuclear Power Corporation of India Limited

Prak Byeong-Ho Korea [email protected] KEPCO Engineering & Construction

company

Prabhakar Jain India [email protected] Heavy Water Board

Prasad Y V D India [email protected]

Nagarjuna university

Pushpalata Rajesh India [email protected] Bhabha Atomic Research Centre

Rachna N. Dave India [email protected] Bhabha Atomic Research Centre









mailto:svn.1948@gmail


mailto:nilesh.patel@adani

mailto:osamu.shibasaki@toshiba





Radhakrishnan R K India [email protected] Nuclear Power Corporation of India Limited

Raghavendra India [email protected] Bhabha Atomic Research Centre

Rajamohan R India [email protected] Bhabha Atomic Research Centre

Rajesh Kumar India [email protected] Bhabha Atomic Research Centre

Rajput M M India [email protected] Bhabha Atomic Research Centre

Rajnish Kumar India Atomic Energy Regulatory Board

Ramakrishnan R India [email protected] Bhabha Atomic Research Centre

Rangarajan S India [email protected] Bhabha Atomic Research Centre

Ranjana Kusari India Nuclear Power Corporation of India Limited

Rao K V India [email protected] Bhabha Atomic Research Centre

Ravi K V India [email protected] Bhabha Atomic Research Centre

Ravidranath India [email protected] Nuclear Power Corporation of India Limited

Rout D India [email protected] Nuclear Power Corporation of India Limited

Rufus A L India [email protected] Bhabha Atomic Research Centre

Sahu B S India [email protected] Nuclear Power Corporation of India Limited

Santanu Bera India [email protected] Bhabha Atomic Research Centre

Santhakumar M India [email protected] Bhabha Atomic Research Centre

Saravanan T India [email protected] Bhabha Atomic Research Centre

Sathyaseelan V S India [email protected] Bhabha Atomic Research Centre

Satinath Ghosh India [email protected] Atomic Energy Regulatory Board

Selvam T India [email protected] Bhabha Atomic Research Centre

Selvavinayagam P India [email protected] Nuclear Power Corporation of India Limited

Sengupta B India [email protected] Nuclear Power Corporation of India Limited

Seshadri H India [email protected] Atomic Energy Regulatory Board

Seunghyun Kim Korea [email protected]

Ulsan National Institute of Science and

Technology,

Sharma R S India [email protected] Bhabha Atomic Research Centre

Shetty P S India [email protected] Bhabha Atomic Research Centre

Shiv Raj Saran India [email protected] Bhabha Atomic Research Centre

Shivakamy K India [email protected] CWMF, Kalpakkam

Shreekumar B India [email protected] KARP, Kalpakkam

Shruti Aich India [email protected] Bhabha Atomic Research Centre

Sinu Chandran India [email protected] Bhabha Atomic Research Centre

Sreevidya N India [email protected] Indira Gandhi Centre for Atomic Research

Srinivasa Rao G India - KARP, Kalpakkam

Srinivasan G India [email protected] Indira Gandhi Centre for Atomic Research

Srinivasan M P India [email protected] Bhabha Atomic Research Centre

Sriyuthamurthy P India [email protected] Bhabha Atomic Research Centre

Subba Rao T India [email protected] Bhabha Atomic Research Centre

Subrajit Tiwari India AUGF, Kalpakkam

Subramanian H India [email protected] Bhabha Atomic Research Centre

Subratabera India [email protected] Atomic Energy Regulatory Board

Sudakar Rao A India [email protected] Heavy Water Board

Sudha R India [email protected] Indira Gandhi Centre for Atomic Research

Sudhir K. Shukla India [email protected] Bhabha Atomic Research Centre

Sujit Basak India Bhabha Atomic Research Centre

Sumathi Suresh India [email protected] Bhabha Atomic Research Centre

Suresh K India [email protected] Nuclear Power Corporation of India Limited

Suriyanarayanan A India [email protected] Indira Gandhi Centre for Atomic Research


















Surya Rao S India [email protected] Heavy Water Board

Swapan Kumar Mahato India [email protected] Indira Gandhi Centre for Atomic Research

Thorat D D India [email protected] Bhabha Atomic Research Centre

Tripathi V S India [email protected] Bhabha Atomic Research Centre

Upadhyay S K India [email protected] Nuclear Power Corporation of India Limited

Veena Subramanian India [email protected] Bhabha Atomic Research Centre

Velmurugan S India [email protected] Bhabha Atomic Research Centre

Venkatesh P India [email protected] NDDP, Kalpakkam

Venkatraman B India [email protected] Indira Gandhi Centre for Atomic Research

Venugopalan V P India [email protected] Bhabha Atomic Research Centre

Venkata Rao Naidu India [email protected] Nuclear Power Corporation of India Limited

Venkatesh M India [email protected] BioLogic Science Instruments Pvt. Ltd.

Vijayalakshmi S India [email protected] Indira Gandhi Centre for Atomic Research

Vikrant Gupta India [email protected] Institute for Plasma Research

Vinay Chaturvedi India [email protected] KNRPC, Kalpakkam

Vinita Vishwakarmaa India [email protected] Sathyabama University

Vivekanand Dubey India [email protected] Bhabha Atomic Research Centre

Viveknand Kain India [email protected] Bhabha Atomic Research Centre

Xinqiang Wu China [email protected] Institute of Metal Research, Chinese Academy

of Sciences

Yadav R N India [email protected] KNRPC, Kalpakkam

Yasuhiro Chimi Japan [email protected] Japan Atomic Energy Agency

Yaw-Ming Chen Taiwan [email protected] Industrial Technology Research Institute,

Yosuke Katsumura Japan [email protected], [email protected]

Japan Radioisotope Association

Yusa Muroya Japan [email protected] Institute of Scientific and Industrial Research,

Osaka University,

Yutaka Watanabe Japan [email protected] Tohoku University









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