current status and perspectives of nuclear reactor based research in bangladesh · 2008-12-04 ·...
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Current status and perspectives of Nuclear reactor based research in Bangladesh
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NuclearSafety &RadiationControl
Department
RTML,Chittagong
BSMEC,Cox’s Bazar
14 NuclearMedicine
& ultrasoundCentres
AECDhaka
AERESavar
OrganogramBangladesh Atomic Energy Commission
1. Institute of Nuclear Science & Technology 6. Institute of Electronics2. Institute of Food & Radiation Biology 7. Institute of Computer Science3. Reactor Operation & Maintenance Unit 8. Central Engineering Facilities4. Tissue Banking & Biomaterial Research 9. Central Library5. Nuclear Minerals Unit
BAECHeadQuarterDhaka
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Institute of Nuclear Science & Technology
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ReactorPhysics &Engineering
Radio-Isotope
Production
ReactorEngineering& Control
LibraryAdministration
Reactor andNeutron Physics
Nuclear &RadiationChemistry
IsotopeHydrology
RadiationMonitoring& Waste
Management
INST
NAA NS NR
Division
Division
Division
Division
Division
Division
Division
OrganogramInstitute of Nuclear Science & Technology
Radio-Isotope
Production
NAA NS NR Utilization of Research Reactor
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Nuclear Reactor available in Bangladesh:
Only a 3MW TRIGA Mark-II Research Reactor
TRIGA Mark II Reactor
Criticality Date : 14 Sept. 1986
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Fuel ElementGraphite Dummy ElementControl RodDry Central ThimbleRabbit TerminusNeutron Source
Reactor core configuration
Rotary Specimen RackTRIGA Mark II Reactor
Rabbit Room
Nuclear Reactor available in Bangladesh:
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Reactor Tank
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Beam ports:
Radial piercing(TAS-NS)
Tangential(NR)
Radial-2
PGNAA(under processing)
Radial-1HRPD (under processing)
Thermal column(unutilized)
Nuclear Reactor available in Bangladesh:
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GraphiteReflector6 rods of B4CControl rod
Fuel elements = 93;IFE = 02; FFCR = 05
Core loadingDemineralized waterCoolant100No. of fuel elementNatural/ForcedCooling19.7 wt%235U enrichmentU-ZrH1.6Fuel moderator material3 MW (thermal)Power output
Technical Data of BAEC TRIGA Reactor
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87.01 Ci(131I, 99mTc, 46Sc)
Radioisotope produced
1274No. of irradiation request catered
15017 MWhTotal burn—up 2444Hours at full power operated 7412Total hours operated 6Hours operated per day
Operation and Utilization Data
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1.2×1051.32×1072.64×10131.39×10137.53×1013Thermal
-Radial piercing beam port2.18×105Tangential beam port1.23×1012Pneumatic Transfer System6.59×1011RSR (Lazy Suzan)3.81×1012DCTEpithermal Position
Neutron Flux (n.cm-2.sec-1)
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Low PowerOperation(NAA, NR)
250-500 kWOperator training
SUN MON TUE WED THU
Present Reactor Operation Schedule
High Power Operation for RI Production, NS and NAA
(3 MW)
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RadioisotopeProduction
Utilization of3MW TRIGA RR
ActivationAnalysis
NeutronRadiography
ManpowerTraining
NeutronScattering
AcademicResearch
Areas of Utilization
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Radioisotope Production
The objective of Radioisotope Productionis to fulfill the local demand of
short-lived medical radioisotopesand radiopharmaceuticals
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– Tc-99m generator production plant– I-131 production plant– I-131 Capsule production facility– QA/QC facility
Major Facilities of Radioisotopes Production
Radioisotope Production
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Thyroid ablation Therapy
~ 1.5 Ci/weekIodine-131 Capsule
For diagnosis of thyroid disorder and therapy of
thyrotoxicosis
~ 1Ci/weekIodine-131 solution
Some centres require weekly and others require
fortnightly
18 generators/ week
Tc-99m Generators (450 mCi)
RemarksDemandRadioisotopes
Supply in 14 Nuclear Medicine Centres and four private hospitals
Radioisotope Production
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Tc-99m Production Facility On-Line Control Software
Radioisotope Production
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Tc-99m Generator Shipment package ofTc-99m generator
Isotope Production
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I-131 production facility I-131 CapsuleProduction Facility
Isotope Production
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Triple Axis Spectrometer
Neutron Scattering
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� Neutron Powder Diffraction StudiesFor structural characterization of materials like metals, metallic oxides, alloys, ceramics, superconductors and various types of magnetic materials
� Small Angle Neutron Scattering (SANS)For determining shape, size and molecular weights of particles in various kinds of biological aggregates and polymers
� Texture StudiesFor identification of texture in industrial and structural materials
Present Scope of ResearchNeutron Scattering
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Neutron Diffraction Pattern of Ni-Zn Ferrite
Neutron Scattering
Neutron Diffraction Pattern of Ni-Zn Ferrite
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Neutron Radiography
Neutron Radiography setup Dark Room Facility
Nondestructive testing of various materials and quality control of industrial products
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Objectives:Objectives:•• Detection of voids, cracks, internal continuity Detection of voids, cracks, internal continuity in materials and industrial products;in materials and industrial products;
•• Detection of defects and corrosion in aircraft Detection of defects and corrosion in aircraft spare parts;spare parts;
•• Determination of defects and water absorption Determination of defects and water absorption behavior of building materials, wood and jute behavior of building materials, wood and jute plastic composites;plastic composites;
•• Study the boron deficiency in different types of Study the boron deficiency in different types of plants, etc.plants, etc.
Neutron Radiography
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1. Elemental analysis of various sample matrices
2. Nuclear Data measurements
Activities
Using NAA technique we work on:
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1. R & D works
2. Services
3. Projects
4. Academic collaboration
ActivitiesThe activities of NAA laboratory are classified into four categories:
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Example of R & D work
Case study-1
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Launching of NAA lab: 1986
TRIGA Mark II Reactor
Elemental analysis
3 MW TRIGA Reactor
Nuclear data measurements
14 MeV Neutron Generator
NAA Group
Example of R & D work
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TRIGA Mark II Reactor
Radial piercingbeam port
BAECTRIGA Reactor Triple Axis Spectrometer
Example of R & D work
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Recently, we have opened a new arena by utilizing the same beam port for determination of neutron capture cross sections at a “rare” thermal energy
(0.0536 eV) region using NAA technique“rare”
The term ‘rare’ means that there are no experimental neutron capture cross-section data available at our
investigated energy
Example of R & D work
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So far, we have successfully carried out two experiments in determining the neutron capture cross section for 186W(n,γ)187W and 71Ga(n,γ)72Ga
reactions at thermal energy of 0.0536 eV
Worldwide several authors reported experimental neutron capture cross sections for various targets at
average thermal energy of 0.0253 eV
Using Cd-cut-off energy
Complex Large uncertainty
Example of R & D work
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ExperimentalIn determining neutron capture cross section using NAA technique, several steps are involved:
�calculation of neutron flux and cross section
�choice of neutron source�sample preparation and irradiation�gamma ray counting and peak analysis�construction of full energy photo peak detection efficiency curve at reference position where true coincidence effects are negligible
Example of R & D work
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Ga2O3-TargetR ea ct or
Au-monitor
Inpile collimator
Shield
MonochromatorCu200
Monochromatic beam(Thermal, 0.0536 eV)
λ = 1.236 A0
Choice of neutron source
Cross sectional view of the arrangement for monochromatizationof reactor neutrons and experimental setup
TRIGA Reactor
Example of R & D work
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TungstenPhysical form: foilPurity: 99.99%Weight: 796 mgSize: 10 mm dia
200µm thickIsotopic compositions: 180W(0.12%), 182W(26.49%)183W(14.31%), 184W(30.64%)
186W(28.42%)
Sample preparationGallium
Physical form: Ga2O3(made in pellet)
Purity: 99.99%Weight: 1.27 gSize: 1.2 cm dia
0.13 cm thickIsotopic compositions:
69Ga(60.108 %)71Ga (39.892 %)
Example of R & D work
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Reactor power: 3 MW (during isotope production)Irradiation time: 5 h
Neutron energy: 0.0536 eV
Irradiation
The cadmium covered gold foil and bare aluminum foil were also irradiated to check the effect of epithermal and fast neutrons.
Simultaneous irradiation of target and gold foil under the following conditions:
Example of R & D work
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Gamma ray counting and peak analysis
ORTEC DSPEC JrTM Digital gamma spectrometry coupled with Canberra HPGe detector of 15%
relative efficiency and 1.9 keV resolution
Counting
Tungsten:10 hours3 times
Gallium:5 hours3 times
AcquisitionSoftware:Maestro-32ORTEC
Peak analysisSoftware:
Hypermet PCV5.12
Example of R & D work
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Gamma ray spectrum of tungsten target
Tungsten
Example of R & D work
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834.
0 k
eV
Gamma ray spectrum of gallium target
Gallium
629.
9 ke
V
Example of R & D work
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y = -0.8639x2 + 3.4219x - 4.3498R2 = 0.9972
y = -3.9854x2 + 17.054x - 19.226R2 = 0.9999 y = -0.85x + 0.9283
R2 = 0.9995
-2
-1.8
-1.6
-1.4
-1.2
-1
-0.8
1.8 2 2.2 2.4 2.6 2.8 3 3.2 3.4
Log (Gamma Energy, keV)
Log (
Effic
iency
, %)
Efficiency curve at 30 cm distance from the detector surface
Point sources used: 22Na, 57Co, 60C0, 54Mn, 133Ba, 137Cs and 152Eu Energy covered: 80.9 – 1408 keV
Example of R & D work
Construction of efficiency curve
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Nuclear Data
95.6324.8
834.03629.96
14.1 h71Ga(n,γ)72Ga
21.827.3
479.55685.73
23.72 h186W(n,γ)187W
95.5411.82.695 d197Au(n,γ)198Au
Branching Ratio (%)
Gamma Energy (keV)
Half-life
Nuclear Reaction
Example of R & D work
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Determination of neutron flux
φ(E) = Asat/σ(Epeak)Asat = saturated activity of gold foilσ(Epeak) = cross section at the peak neutron energy (68.5 barn at 0.0536 eV)
In case of monoenergetic thermal neutrons, the flux φ(E) can simply be obtained as:
Assuming the self attenuation factor for gold foil at 0.0536 eV is negligible
Example of R & D work
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)1).(1.(....
231002.6 ctitwtA
w
dtpee
eNsatA λλθ
γ
λ
ε
λ−−×××
+
−−Ι=
Neutron flux for tungsten ~ 1.41×105 n.cm-2.s-1
Neutron flux for gallium ~ 1.73×105 n.cm-2.s-1
Determination of neutron flux
Example of R & D work
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g
satpeak FE
AE ).()( φσ =
Fg = correction factor for gamma attenuationwithin the sample
µ = linear attenuation coefficient (cm-1)
Determination of neutron cross section
Fg
xg exF µµ−
−=1
Fg
Example of R & D work
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Results
We report new cross sections for186W(n,γ)187W reaction = 26.6±2.5 b
71Ga(n,γ)72Ga reaction = 2.75±0.14 b
These are the first experimental values at 0.0536 eVneutron energy for the tungsten and gallium targets
Example of R & D work
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0
10
20
30
40
50
60
0.01 0.03 0.05 0.07 0.09Neutron energy (keV)
Cross
secti
on (b
)
ENDF-VI.8 JENDL-3.3This work Mughabghab'84Karadag'04 Gillitte'66Pomerance'52 Seren et al.'47Friesenhahn et al.'66 Anufriev et al.'81Damle et al.'67 Erdtman'76Gleason'77 Heft'78Hogg'70 Kafala et al.'97Knof'87 Lyon'60Simonits et al.'84 Friesenhahn et al.'66
Neutron capture cross section for the 186W(n,γ)187W reaction
186W(n,γ)187W
Example of R & D work
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Neutron capture cross section for the 71Ga(n,γ)72Ga reaction
0
2
4
6
8
10
0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 0.09 0.10Neutron energy (eV)
Cross
secti
on (b
)ENDF/B-VII JENDL-3.3This work KaradagHolden KoesterSimonits MughabghabGleason RyvesPomerance HarrisSeren
71Ga(n,γ)72Ga
Example of R & D work
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The results accepted for publications in the reputed report and journals is a testimony of our claim
Our technique is very simple to obtain data with good precision and accuracy
We can apply the technique for other targets
Example of R & D work
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“Utilization of Radial Piercing Beam port of TRIGA Reactor for Nuclear Data Measurements”
S.M. Hossain, M.S. Uddin,, Sk.A. Latif, M.A. Hafiz, M.A. Islam, M.M.H. Chowdhury, M.A. Ali, A.K.M. Zakaria, S.M. Yunus and F,U, Ahmed
Internal Report INST-115/RNPD-27, April 2008
“Measurement of thermal neutron cross section for the 186W(n,γ)187W reaction by the activation technique”
M.S. Uddin, M.M.H. Chowdhury, S.M. Hossain, Sk.A. Latif, M.A. Hafiz, M.A. Islam, A.K.M. Zakaria and S.M. Azharul Islam
Appl. Radiat. Isot. 66 (2008)1235-1239
Example of R & D work
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Measurement of neutron capture cross section of the 71Ga(n,γ)72Ga reaction at 0.0536 eV energy
M.S. Uddin, M.M.H. Chowdhury, S.M. Hossain, Sk.A. Latif, M.A. Hafiz, M.A. Islam, A.K.M. Zakaria, S.M. Yunus and S.M. Azharul Islam
Nucl. Inst. Meth., Phys. Res. B 266 (2008)3341-3345
Example of R & D work
Thermal neutron capture cross sections for the 152Sm(n,γ)153Sm and 154Sm(n,γ)155Sm reactions at 0.0536 eV energy
M. S. Uddin, M. H. Chowdhury, S.M. Hossain, Sk. A. Latif, M. A. Islam, M.A. Hafiz, S.H. Mubin, A. K. M. Zakaria, S. M.
Yunus and S. M. Azharul Islam
Nucl. Inst. Meth., Phys. Res. B, 266 (2008) 4855-4861
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Example of R & D work
Case study-2
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Case Study-2Comparison of analytical results of Bay of Bengal
Sediments with agricultural soils of Bangladesh
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Sediment sampling points in Bay of BengalExample of R & D work
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F.V. Seabird used for collectingSediment samples from the Bay
of Bengal.
KC KC KajakKajak Corer for Corer for collecting muddy sedimentcollecting muddy sedimentGPS receiver
Example of R & D work
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12.8Open92°20'28" E20°37'48" NStation 0650Open92°11'48" E20°30'56" NStation 0540.7Open91°52'39" E20°52'10" NStation 0426.7Open91°46'10" E21°22'38" NStation 0320.7Open91°39'48" E21°37'10" NStation 0212.3Open91°39'54" E22°06'54" NStation 01
longitudelatitudeGround
Depth (m) *Type of Sea
Geographical positionStation
Table. Geographical position (latitude, longitude),depth of the sampling stations
* Depth (m) of ground from where sediment was collected
Example of R & D work
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Soil sampling from sugar-cane and paddy field
Geological cross section of soil sampling area
Example of R & D workAgricultural soil sampling
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QC of Analysis of Agricultural soils using NAA
0 300 600 900 1200 1500 1800 2100 2400 2700 3000100
101
102
103
104
105
IAEA-Soil-7Irradiation Channel: HR-T-B pipe of JRR4Irradiation time: 40 minGamma spectrometry: R4S1 (GX-2018)Decay time: 4 daysCounting time: 4000 secSource to detector distance: 10 cm
140 La
, 815.0 keV
140 La
, 328.8 keV
46Sc, 889.3 keV
46Sc, 1120.5
keV
Single
escap
e of 2
754.0
keV
Double e
scape
of 2754.0 keV
24Na
, 2754.0
keV
140 La
, 1596.2
keV
42K, 15
24.7 keV
76As
, 559.2 keV
140 La
, 487.0 keV
153 Sm
, 103.2 keV
24Na
, 1368.6
keV
Coun
ts
Gamma-ray Energy (keV)
IAEA Soil-7Irradiation Channel: RSR of reactorIrradiation time: 4 hoursγ-spectrometry: HPGe with DSpecCounting time: 4000 secDecay time: 4 days
Example of R & D work
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0500
10001500
20002500
300010
0
101
102
103
104
105
60Co, 1332.5 keV
60Co, 1173.2 keV
233Pa, 312.2 keV
153Sm, 103.2 keV141Ce, 145.4 keV
140La, 815.8 keV
140La, 328.8 keV140La, 487.0 keV
76As, 559.1 keV
58Fe, 1291.6 keV
58Fe, 1099.2 keV46Sc, 1120.5 keV
46Sc, 889.3 keV
24Na, 2754.0 keV
24Na, 1368.6 keV
140La, 1596.2 keV42K, 1524.2 keV
Counts
Gamma-ray Energy (keV)
NIST Coal Fly AshQC of Analysis of Agricultural soils using NAA
Example of R & D work
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QC of Analysis using NAA
Na Al K Sc Ti V Cr Mn Fe Co As Rb Sr Sb Ba Hf La CeSmEu Dy Yb Th0.6
0.7
0.8
0.9
1.0
1.1
1.2
1.3
1.4
10%
NIST CRM Coal Fly Ash 1633bIrradiation: 10 sec & 10 minChannel: PN-3 of JRR-3Detector: PN3B
5%
Ratio
of M
easu
red
to C
ertif
ied
conc
.
Element
NIST Coal Fly AshRelative to IAEA-Soil-7
QC of AnalysisExample of R & D work
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Comparison of arsenic concentrationdetermined by NAA and AAS in sediment
+ 304.456.35Station-55.95
5.116.457.786.16
AAS
+ 5212.29Station-6
+ 398.38Station-4+ 197.92Station-3+ 88.46Station-2+ 4010.20Station-1
Deviation %
NAA (mean of two folds)
Sample code
Concentration of As (mg/kg)
Example of R & D work
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Comparison of chromium concentration determined by NAA and AAS in sediments
+ 5367.88144.2Station-592.90
98.1793.54117.8107.9
AAS
+ 29130.6Station-6
+ 32145.1Station-4+ 18114.5Station-3- 3488.11Station-2- 1296.18Station-1
Deviation %
NAA (mean of two folds)
Sample code
Concentration of Cr (mg/kg)
Example of R & D work
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+ 1713.7716.58Station-59.38
14.1918.4325.0118.61
AAS
+ 5018.88Station-6
+ 2017.82Station-4- 817.09Station-3- 4717.06Station-2- 318.11Station-1
Deviation %
NAA (mean of two folds)
Sample code
Concentration of Co (mg/kg)
Comparison of cobalt concentration determined by NAA and AAS in sediments
Example of R & D work
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Comparison Sediments with soils using NAA
0.459 %7270.68219.964.97818.771036.32
Agricultural soils mg/kg
Sed<soil (0.4%)Sed<soil (26%)Sed>soil (22%)Sed<soil (24%)Sed<soil (40%)Sed<soil (6.3%)Sed>soil (17%)Sed>soil (41%)
Comparison
0.457 %Ti 538Mn0.829Sb15.12Th2.970U17.59Co120Cr8.933As
Sediments Bay of
Bengal mg/kg
Element
Example of R & D work
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Conclusion
High concentrations of
- U and Th in agricultural soil may be due to use of chemical fertilizers like Triple Super Phosphate (TSP), Gypsum, Diammoniumphosphate (DAP), etc.
- As, Sb and Cr in Bay of Bengal sedimentsdue to marine pollution
Example of R & D workComparison Sediments with soils using NAA
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Case Study-3Monitoring of Environmental
Contaminants due to Shipbreaking
Just Started!!!
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What is Ship breaking?
�After 25-30 years ships are at the end of their sailing life
� These ‘End of Life Vessels’ are sold and dismantled to recover the valuable steel
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When started this idea?�In the 1970s shipbreaking was concentrated in Europe
�Performed at docks, it was a highly mechanisedindustrial operation
�But the costs of upholding environmental, health and safety standards increased, the shipping industries moved to developing Countries
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What’s the situation in Bangladesh?
�Bangladesh is dependent on ship breaking for its domestic steel requirements
�The ship breaking industry is not subject to any environmental laws or health and safety regulations for workers
�Chittagong ship breaking yards are highly polluted coastal belt of 20 km
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What’s the situation in Bangladesh?Map
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How does shipbreaking pollute environment ?
�About 95% of the ship consists of steel coated with paint containing lead, cadmium, organotins, arsenic, zinc and chromium.
�Ships also contain a wide range of other hazardous wastes, PCBs, asbestos, residual oil, etc.
In Bangladesh, ships containing these materials are being cut up by hand, on open beaches, with
no consideration given to safe and environmentally friendly waste management practices
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A worker working barefoot without any protective
footware
How does shipbreaking pollute environment ?
Workers carrying a piece of broken steel without any hand
gloves
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How does shipbreaking pollute environment ?
Heavy metals
�The workers can have toxic effect from heavy metals like cadmium, organotins, arsenic, zinc and chromium which may find in many parts of ships such as in paints, coatings, anodes and electrical equipment�Marine environment can also be contaminate
�Exposure can result in lung cancer, cancer of the skin, intestine, kidney, liver or bladder. It can also cause damage to blood vessels
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How does shipbreaking pollute environment ?
Persistent Organic Pollutants (POP's)
� Shipbreaking activities are a source of lethal POPs.
�POPs are chemicals that are highly toxic, remain intact in the environment for long periods
�POPs become widely distributed geographically, bioaccumulate through the food web, accumulate in the fatty tissue of living organisms and pose a risk of causing adverse effects to the human population, wildlife and the environment.
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How does shipbreaking pollute environment ?
Asbestos
�Asbestos was used in old ships as a heat insulator
�As there are no asbestos disposal procedures, during scrapping, workers and the surrounding environment are exposed to the asbestos fibers
� Exposure to asbestos fibers (even in very low concentrations) especially through inhalation may cause cancer and asbestosis.
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How does shipbreaking pollute environment ?
Oil pollution�As a result of breaking the ships, oil residues and the other refuses are being spilled, mixed with the sea water and left floating along the entire seashore
�Oil films on water reduce the exchange of oxygen and carbon dioxide across the air-sea interface which is harmful to aquatic life
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How does shipbreaking pollute environment ?
Indiscriminate expansion of ship breaking activities poses a real threat to the coastal
inter-tidal zone and its habitat.
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What’s our progress ?We have collected samples from the workers
working in 5 different shipyards:
- 20 hair samples
- 20 nail samples
From the same 5 shipyards we have also collected:
- 15 soil samples (3 samples from each yard)
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What’s our progress ?We are doing this research work in collaboration
with Chittagong University
ChittagongUniversity
Shipyards
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ServicesInternal
(without fee) External(with fee)
Different researchGroup of BAEC
For thermal, epithermal and fast neutron flux mapping in different
irradiation locations;Irradiation capsules development;Improvement of irradiation
conditions for RI production, etc.
Arsenocosis patients
DoE, Govt. & NGOs, Universities, etc.
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Arsenocoisis patientsServices
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As concentration in hair of some arsenocoisis patients
4.3±0.33Prof. Dr. A.Z.M. Maidul Islam, Head of Skin & V. D. Department, BSMM University
Mis Amena, age: 16Y, P.S. and Dist.: Chandpur.
3
5.31±0.32Dr. Mansurul Alam, Department of Dermatology & STDs, Chittagong Medical College & Hospital
Mr. Nasir Uddin, age: 35Y, P.S.: Brahman Para, Dist.: Comilla
2
36.4±1.5Dr. Mir Nazrul Islam, Consultant Dermatologist, BIRDEM Hospital
Mrs. Parveen Begum, age: 26Y, P.S.: Bhanga, Dist.: Faridpur
1
Arsenic Conc. µg/g
Referred by DoctorPatient IdentityCase No.
Normal value of As in human hair is less than 1 µg/g
Services
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As concentration in hair of some arsenocoisis patients
1.73±0.14Dr. Mir Nazrul Islam, Consultant Dermatologist, BIRDEM Hospital
Mr. Jahangir Hossain age: 26Y, P.S. and Dist.: Chandpur.
6
3.64±0.41Dr. Kamrul Hasan Zaigirder, Skin & STD’s. Department, BSMM University, Dhaka
Mr. Zahirul, age: 32Y, P.S.: Faridganj, Dist.: Chandpur
5
25.5±5.1Prof. Dr. A.Z.M. Maidul Islam, Head of Skin & V. D. Department, BSMM University
Mrs. Sabina Zaman, age: 34Y, P.S. and Dist.: Gopalganj
4
Arsenic Conc. µg/g
Referred by DoctorPatient IdentityCase No.
Services
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Projects1. IAEA TC project: BGD/8/018 “Isotope techniques formitigating arsenic in ground water (NAA component)”
- Recently completed
2. ADP of Bangladesh Govt. Project: Strengthening theUtilization of TRIGA Reactor
- On going3. ADP (BGD Govt.) Project: Strengthening the Utili-zation of 3MW TRIGA Mark-II Research Reactor
- On going
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Academic Collaboration
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1. M. A. Hafiz – Dept. of Physics, BUET2. Md. Matiur Rahman - Dept. of Physics, Jahangirnagar University3. Rezaur Rahman – Dept. of Physics, Jahangirnagar University4. M.M.H. Chowdhury - Dept. of Physics, Jahangirnagar University
Current students in NAA labPh.D.
M.Phil.1. M. A. Salam - Dept. of Physics, Jahangirnagar University2. M. A. Rouf – Dept. of Physics, BUET
M.Sc.1. Md. Kamal Hossain– Dept. of Physics, Chittagong University2. Ratneshar - Dept. of Physics, SUST3. Saifur – Dept. of Env. Sciences, Jahangirnagar University4. A. Kadir - Dept. of Env. Sciences, Jahangirnagar University5. Amina Khatun - Dept. of Physics, Jahangirnagar University
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# Although the BAEC TRIGA reactor has been operating since 1986, but because of several limitations its optimum utilization could not be achieved yet.
# The radial beam ports 1 & 2 and thermal column are still lying unutilized.
Future Trend
However, in order to optimize its utilization, several initiatives have taken.
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A high resolution powder diffractometer (HRPD) is being installed at the radial beam port-1 under an ADP (Annual Development Program) Project financed by the Government of Bangladesh.
Future Trend
Schematic Diagram of Proposed HRPD
Expected Resolution:∆d/d ~ 1.5x10-3at 2θ ≈ 80°
Scanning Range (2θ): ≈ 120°
A pattern recording Time:6-8 h
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Future TrendA digital neutron radiography setup is being installed at the
tangential beam port under the same ADP project
Proposed electronic imaging System
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Future Trend
# A project has also been submitted under the ADP program for installation of PGNAA.
# The present analog console of the reactor will be replaced by a digital one under an ongoing ADP project.
# The establishment of 99mTc kit production laboratory is also under process in the frame work of a separate ADP project.
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Conclusion# Since its establishment, the BAEC TRIGA
reactor has been utilized without any major incident.
# However, a few minor incidents sometimes hampered the operation of the reactor.
# For instance, the N-16 decay tank (DT) leakage problem that arised due to pitting corrosion at several areas of the DT caused by rainwater suspended the operation of the reactor at high power level for about 4 years (from 1997 to 2001).
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Conclusion
# With limited facilities, different utilization groups have been trying for proper utilization of BAEC TRIGA reactor in both fundamental research and service purposes.
# But, in reality, the neutrons generated in the reactor core cannot be exploited efficiently using the present experimental facilities and, as a result, the optimum utilization of the BAEC TRIGA reactor is not being possible.
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Conclusion
Under these circumstances, it is strongly felt that measures have to be taken up so as to update and extend the laboratory facilities with the help of national and international strategic partners.
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