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2005-05-27 (Delhi, Petrofed) RKS - India's Energy Security - The Role of Nuclear Energy 1

India’s Energy Security – The Role of Nuclear Energy

Ratan K. SinhaDistinguished Scientist and Director,

Reactor Design & Development Group,BARC

Guest Lecture at Petroleum Federation of India, New Delhi

May 27, 2005


BARCBARC Organisation of Atomic Energy Commission


BARCBARC

19 Groups 71 Divisions

14900 Total Staff Strength 4130 Scientists/ Engrs.

200 Acres Area 10000 sq. m. developed gardens.

Bhabha Atomic Research Centre


BARCBARC

• Indigenous development of nuclear technology

- for generating energy

- for non-power applications

• Research, Development, Demonstration and Deployment - RD3

- Fruits of research handed over for exploitation on industrial scale by NPCIL, NFC, HWB, IREL, UCIL AND ECIL

• Pursue excellence in all areas of nuclear science and technology

- Utilisation of research reactors

- Front and back end of nuclear fuel cycle

- Production of radioisotopes and development of radiation

technology

Goals of R&D Activities in BARC


BARCBARC Scope of my talk today

In the available time, I intend to cover the following:

Energy Security and Nuclear Energy

The Physics behind Nuclear Power

The Indian Nuclear Power Programme and its Rationale.

The Indian Advanced Heavy Water Reactor – An illustration of the Philosophy Behind Design & Development of Advanced Nuclear Reactors.

The Indian Programme for Generation of Hydrogen using Nuclear Energy


BARCBARC

Energy Security and Nuclear Energy


BARCBARC “There is no power as costly as no-power” – Homi Bhabha

10 100 1000 1000030

40

50

60

70

80 Japan

U.S.A.

India (1951-60)

India (1961 -70)

India (1980-85)

India (1997)

Source of the Data:World Bank, 1999Li

fe E

xpec

tanc

y at

Bir

th (y

ears

)

Electricity Consumption per Capita (kWh/year)


BARCBARC Nuclear Power is the greatest facilitator of energy security in countries with inadequate domestic energy resources

REACTORREACTOR

Requirement of natural uranium for a 1000 MWe Nuclear Power Plant: ~ 160 t /Year.

Requirement of coal for a 1000 MWe Coal fired plant ~ 2.6 million t / Year (i.e. 5 trains of 1400 t /Day)


BARCBARC 'The ice is melting much faster than we thought'

“Even if they (opponents of nuclear energy) were right about its dangers, and they are not, its worldwide use as our main source of energy would pose an insignificant threat compared with the dangers of intolerable and lethal heat waves and sea levels rising to drown every coastal city of the world.

We have no time to experiment with visionary energy sources; civilisation is in imminent danger and has to use nuclear - the one safe, available, energy source - now or suffer the pain soon to be inflicted by our outraged planet.”

- Eminent Environmental Scientist, James Lovelock, The Independent, May 24, 2004•Greenland Picture: http://earthobservatory.nasa.gov/Newsroom/NewImages/images.php3?img_id=15341


BARCBARC Nuclear Power in the World Today

•First commercial nuclear power stations started operation in 1950s.

•440 commercial nuclear reactors operating in 31 countries

•360,000 MWe is the total capacity. •Supply of 16% of the world's electricity

•56 countries operate a total of 284 research reactors.


BARCBARC Development of Nuclear Power - Chronology

1970's – Oil Shock

1979 - TMI Accident

1986 - Chernobyl Accident

Major Events Affecting Growth of Nuclear Power

1990's – Liberalisation of electricity marketand availability of cheap gas


BARCBARC Some Data for the Top Twelve GDP Ranking Countries

Country GDP Rank

Electricity Prodn. Rank

Per Capita Elec. Gen. (kWh/yr)

bn kWhNuclear2003*

% Nuclear

Reactors under constn.

Installed MWe per Te U/Yr reqd.

USA 01 01 12824 763.7 20 0 4.4

China 02 02 1104 79.0 1.4 3 5.1

Japan 03 03 8152 230.8 39 3 5.8

India 04 05 610 16.4 3.7 9 (8 now) 8.5

Germany

05 07 6616 157.4 30 0 5.6

France 06 08 8642 420.7 78 0 6.2

UK 07 09 6006 85.3 22 0 4.9

Italy 08 12 4462 0 0 0

Russia 09 04 5858 138.4 16 6 6.9

Brazil 10 10 1765 13.3 4.0 0 6.1

S. Korea 11 11 6020 123.3 39 2 5.3

Canada 12 06 17581 70.3 12 0 7.1

WORLD 2356 16 29 5.4

Sources: 1. Uranium Information Centre, Australia http://www.uic.com.au/reactors.htm 3. *WNA• 2. CIA World Fact Book 2003 (Electricity Prodn. 2001, Population 2003)


BARCBARC We can draw some interesting inferences from the data for the twelve top rankers

GDP and Electricity Generation ranks more or less match – A Strong Correlation. Exceptions – countries with a very cold climate (Russia and Canada)

All the twelve countries have (or have had) a significant nuclear power programme

Countries with no active nuclear construction programmes today have either high per capita electricity generation or access to alternative energy options (cheaper in the short term). Japan : High PCEC, but no domestic fuel resources - active programme. Brazil: Low PCEC, but large hydro resources – dormant programme. Italy: Shutdown its existing four Nuclear Power Plants, but imports 20%

of its electricity from neighboring France, which produces 80% of its electricity using Nuclear. Acid rain damaging Italian lakes.

The selection of nuclear reactor technology has a large bearing on the efficient utilisation of available Uranium. India (PHWRs) tops the list in this regard.


BARCBARC Perspective of a country on nuclear energy depends on domestic realities

10 100 1000 10000

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1.0

Ind

ia

Jap

anU

. S

. A

.

H

uman

Dev

elo

pm

ent

Inde

x

Per Capita Electricity Consumption (kWh/year)

Source of the Data:World Bank, 1999Human Development Report, 2001

“In general, the perspective of a country on nuclear energy – and degree of public acceptance – could depend on where you are on these curves, on the availability of fossil and hydro resources, and on technological development capacity.”

- R. Chidambaram, 2003


BARCBARC

The three basic concepts of the Physics behind Nuclear Power


BARCBARC 1. Fission

Natural uranium that is mined from the ground is 0.7% U-235 and 99.3% U-238.

Slow Neutrons can initiate a fission of uranium 235 (U-235), an isotope of uranium that occurs in nature.

The result of the fission is

•Fission products that are radioactive, •Radiation, •Fast neutrons (~ 2.5 neutrons per fission)•Heat.


BARCBARC

92U235 +

0n136Kr92 + 56Ba141 + 3(0n1) + Energy

92U235 + 0n142Mo95 + 57La139 + 7(-1e0) + 2(0n1) + Energy

Mass 'm1'= 236.0526 g Mass 'm2'= 235.8332 g

Difference in mass Δm = 0.2194 gm

E = Δm * c2

c, velocity of light = 3 x108

m/s Fission of 1 gm of U-235 per day generates ~1 MW

Power

NeutronNucleus

n

Radiation

Fission Fragments

~200 MeVof Energy

Compound Nucleus in an excited state of high

internal energy

Fast-n

The fission reaction


BARCBARC 2. Moderation

The fast neutrons have a low probability of inducing further fissions (but used as such in fast reactors), and hence generating more neutrons thus sustaining a chain reaction.

So in thermal reactors, we need to slow down the neutrons (i.e., thermalise or moderate them), which we do by using a moderator such as water (Heavy Water or Light water).


BARCBARC Slowing down (thermalisation or moderation) of fission neutrons facilitates lower critical mass, but leads to some loss of neutrons through absorption in the moderator

Energy distribution of fission neutrons peaks at ~ 0.7 MeV with average energy at ~ 1.9 MeV.

Variation of fission cross-section (barns) of U-235 with neutron energy (eV)

ThermalReactors

Fast Reactors

Cross-section: The effective target presented by a nucleus for collisions leading to nuclear reactions .

1 barn = 10-24 cm2


BARCBARC 3. Conversion

Uranium-235 is the only naturally occurring fissile isotope.

Plutonium-239 and Uranium-233 are man-made fissile isotopes which can be produced in a reactor.

Uranium 238 (99.3% of natural uranium) on absorbing neutrons in a nuclear reactor, gets converted to Plutonium-239.

Thorium-232, another naturally occurring element, on absorbing neutrons in a nuclear reactor, gets converted to Uranium-233.

The converted fissile materials (Pu-239 and U-233) can be recovered by reprocessing the spent fuel coming out of a reactor.- Closed Nuclear Fuel Cycle

In breeder reactors (practically, Fast Breeder Reactors) it is possible to produce more fissile material than that gets consumed.


BARCBARC Conversion of fertile material to fissile material is made possible by neutron capture reactions

92U238 + 0n1 92U239+

(Fertile) 93Np239 +

(Fissile) 94Pu239+

(n, )

90Th232 + 0n1 90Th233+

(Fertile) 91Pa233 +

(Fissile) 92U233+

(n, )


BARCBARC Nuclear reactors operating on fission are broadly classified into two types

Classification of Reactor Systems

Thermal Reactors

Fission is sustained primarily by thermal neutrons ( E ~ 0.025 eV).

Moderator (Ordinary water, heavy water, graphite, beryllium) is required to slow down the high energy fission neutrons. Large core.

Very high fission cross-section for thermal neutrons, less fuel inventory.

Fast Reactors

Fission is sustained primarily by fast neutrons (E ~ 1 MeV)

No moderator used. Compact core. High core power density – liquid metal or helium gas as coolant.

Higher number of neutrons available for capture in fertile material. Breeding possible.


BARCBARC There are two options for a “Nuclear Fuel Cycle” :“Open”, and “Closed”

FRESH FUEL

RECYCLED FUELFABRICATION

REPROCESSING

REFINING(U & Th

CONCT.)

235U ENRICHMENT

NUCLEAR POWER PLANT

SPENT FUEL

WASTE CONDITIONING

MINING U & ThORES

CLOSEDCYCLE

OPENCYCLE

WASTE DISPOSAL

Th232,

U238

U233, Pu239

FISSIONPRODUCTS

ENERGY


BARCBARC Main attributes of nuclear energy relevant for electricity and hydrogen generation

Very large resource

Suitable for large unit sizes for meeting urban and concentrated industrial demands

No CO2 emissions

Relatively insensitive to fuel price increase

Capability to produce very high temperature process heat


BARCBARC

The Indian Nuclear Power Programme and its Rationale


BARCBARC Our Goal

Our dream to realise a quality of life for people commensurate with other developed countries -

- Needs generation of 5000 kWh per year per capita, - Demands a total capacity of 7500 billion kWh per year for a population

of 1.5 billion by 2050,- Calls for a strategic growth in electricity generation considering:

• Energy resources, self sufficiency,• Effect on local, regional & global environment,• Health externalities,• Demand profile & energy import scenario.

Our study indicates a necessity to meet more than 1/4th of electricity generation by nuclear.

Nuclear energy will also need to play a progressively increasing role for non- grid-based-electricity applications (hydrogen generation, desalination, compact power packs).

- From a presentation by Dr. Anil Kakodkar in INSAC-2003, Kalpakkam


BARCBARC

For a large country like India, with huge future energy requirements, depending largely upon import of energy resources and technologies is neither economically sustainable nor strategically sound for energy security.

Domestic energy resources must be a major contributor to Indian energy supply.

Dom

esti

c r

esou

rces &

in

frastr

uctu

re

(may g

row

wit

h t

ime)

Low

High

Size of Nuclear Power Programme

Small Large

High incentive for self-reliance

Low incentive for self-reliance


BARCBARC The Indian Energy Resource Base explains our current priority for Closed Nuclear Fuel Cycle and ThoriumResource Amount Potential (GWe-yr)

Coal 38 BT (Extractable) 7614

Oil + OEG 12 BT (5833)

Uranium 61000 T Metal In PHWRs - 328

Thorium 225000 T Metal In FBRs - 42231 In Breeders 225000

Hydro 150 GWe (Name plate) 69/yr

Non-conv. Renewables

100 GWe (Name plate) 33/ yr

Total Solar Insolation

(600,000 GWe.)Ref.: A Strategy for Growth of Electrical Energy in India, DAE, August 2004


BARCBARC India has adopted a closed nuclear fuel cycle for its indigenous programme

To facilitate wide-spread and long term use of nuclear power a sustainable nuclear fuel strategy, based on closed nuclear fuel cycle and thorium utilisation is essential.

Taking cognisance of its resource position, the Indian priority for adopting this strategy has been high.

The Indian nuclear power programme, therefore, has three major stages:

1) Nat. U in PHWRs

2) Pu in FBRs

3) U-233, Th in advanced reactors [a possibility of synergy with Accelerator Driven Systems (ADS)].


BARCBARC The three stage Indian Nuclear Power Programme aims to achieve long-term energy security through self-reliance.

3rd Stage: Thorium-233U based reactors

2nd Stage: Fast Breeder Reactors using Pu as fuel and breeding Pu and 233U.

1st Stage: Pressurised Heavy Water Reactors using Natural Uranium as fuel and producing Plutonium which is recovered in reprocessing plants for initiating the 2nd Stage


BARCBARC

Objective: • Technology absorption, familiarisation and infrastructure

building.

Requirements:

• Affordability - Low capital cost and favourable payment terms.• Security - Assurance of future supplies and support• Technology - Readily available, proven technology; Turn-key

construction

Outcome:

• Two 200 MWe BWRs at Tarapur supplied by GE USA.

Rationale for Import of NPPs - Early Sixties


BARCBARC

Objective:•Long term economics and sustainability for building a large programme.

Requirements:

• Security and Sustainability - security of fuel supply.•Technology - consistent with first stage of a long term vision

- participation of local industry.- willingness to consider a new technology.

Outcome:•Launching a PHWR programme, starting with RAPS-1, a 200 MWe PHWR built with Canadian support.

Rationale for Import of NPPs - Late Sixties


BARCBARC Current Rationale for Import of NPPs

Objective: Augment nuclear share in the energy mix, in the short term.

Requirements: Light water reactors of proven performance Terms acceptable to India Limited number (about 6 GWe)

Outcome: Kundankulam-1 & 2, 2x1000MWe VVER based NPPs from RF


BARCBARC The current Indian nuclear power reactors belong to six different configurations

DIFFERENT POWER REACTOR CONFIGURATIONS

ORDINARY WATER MODERATED REACTORS

PRESSURISED WATER Cooled

HEAVY WATER MODERATED REACTORS

FAST BREEDER REACTORS

BOILING WATER Cooled

PRESSURISEDHEAVY

WATER Cooled

Tarapur 1&2

RajasthanKalpakkam Narora Kaiga Kakarapar, Tarapur

Kalpakkam

GAS COOLED REACTORS

OTHER REACTORS

Kundankulam

BOILING WATER Cooled

AHWR

CHTR


BARCBARC Current status of the Indian nuclear power programme

Stage - IIIStage - III Thorium Based ReactorsThorium Based Reactors

• 30 kWth KAMINI- Oper.30 kWth KAMINI- Oper.• 300 MWe AHWR-300 MWe AHWR-Under developmentUnder development•CHTR – Under design.CHTR – Under design.• POWER POTENTIAL POWER POTENTIAL Very Large. Availability Very Large. Availability of ADS can enable early of ADS can enable early introduction of Thorium introduction of Thorium on a large scale.on a large scale.

Stage - I Stage - I PHWRsPHWRs

• 13- Operating13- Operating• 5 - Under construction5 - Under construction• Several others plannedSeveral others planned• POTENTIAL POTENTIAL 10 GWe10 GWe

LWRsLWRs• 2 BWRs- Operating2 BWRs- Operating• 2 VVERs- Under 2 VVERs- Under constructionconstruction

8582

80

75

7167

60

88

868484

79

75

69

72

88

50

55

60

65

70

75

80

85

90

1995-96 1996-97 1997-98 1998-99 1999-00 2000-01 2001-02 2002-03

Avail

abilit

y/C

apac

ity F

acto

r (%

) ----

->

Stage – II Stage – II FBRsFBRs

• 40 MWth FBTR- Oper.40 MWth FBTR- Oper.• 500 MWe PFBR- 500 MWe PFBR- Under Under constructionconstruction • POTENTIAL POTENTIAL 350 GWe350 GWe

Among the best performing in the world

Largest number of reactors under construction in any country in the world today


BARCBARC Indian Nuclear Power Programme till 2020

REACTOR TYPE AND CAPACITIES CAPACITY (MWe)

CUMULATIVE CAPACITY

(MWe)

13 reactors at 6 sites under operation Tarapur, Rawatbhata,

Kalpakkam, Narora, Kakrapar and Kaiga

3,260 3,260

5 PHWRs under construction at Tarapur (1x540 MWe),Kaiga (2x220 MWe), RAPS-5&6(2x220 MWe)

1,420 4,680

2 LWRs under construction at Kudankulam(2x1000 MWe)

2,000 6,680

PFBR at Kalpakkam under construction (1 X 500 MWe)

500 7,180

Projects planned till 2020 PHWRs(8x700 MWe), FBRs(4x500 MWe), LWRs(6x1000 MWe), AHWR(1x300 MWe)

13,900 21,080


BARCBARC A Study on Projected Growth of Installed Nuclear Generation Capacity using Indigenous Fuel and Technologies

Projected Growth with Indigenous Fuel

0

50

100

150

200

250

2002 2012 2022 2032 2042 2052Year

GW

e

Thermal

Fast

Total

Ref.: A Strategy for Growth of Electrical Energy in India, DAE, August 2004


BARCBARC

The Indian Advanced Heavy Water Reactor – An illustration of the Philosophy Behind Design & Development of Advanced Nuclear Reactors.

At BARC, the design and development of AHWR is currently in an advanced stage.


BARCBARC

Major Design Objectives

1. A large fraction of power from thorium.

2. Deployment of passive safety features – 3 days grace period.

3. No need for planning off-site emergency measures.

4. Power output – 300 MWe with 500 m3/d of desalinated water.

5. Design life of 100 years.

AHWR is a vertical pressure tube type, boiling light water cooled and heavy water moderated reactor using 233U-Th MOX (Mixed Oxide) and Pu-Th MOX fuel.

Advanced Heavy Water Reactor


BARCBARC The 3.5 m long AHWR fuel clusters have a design which is unique in the world.

Bottom Tie Plate

Top Tie Plate

Water Tube

Fuel PinDisplacer Rod

Displacer Rod

Water Tube

(Th- U)O pins

(Th-Pu)O pins233

2

2

Key Features

Thorium bearing fuel [(Th + Pu)O2 MOX, (Th + 233U)O2 MOX]; Enrichment 2.5% (top half) & 4% (bottom half) in the former

Central (ZrO2-Dy2O3) displacer rod

Emergency core cooling water injected into the cluster through the holes in displacer rod

Low pressure drop design

Fuel Cluster Cross-Section


BARCBARC These fuel clusters reside in 452 out of 505 lattice positions in a vertical core having Heavy Water moderator

N Shut off Rod 41

AR Absorber Rod 4

RR Regulating Rod 4

SR Shim Rod 4

30,000 MWd/Te

23,500 MWd/Te

20,000 MWd/Te

245

Dia. 30D

ia.

202

Lattice Position4 x 4

Incore Detector

(Typ.)

Typical incore detector

(36 positions)

452 Fuel Channels


BARCBARC The reactor is located in the basement with four steam drums located at the top

GDWP Header

Moderator System

Tail Pipe Tower

Down comers

Advanced Accumulators

Isolation Condensers

Feeder pipes

MHT Purification system

PW Header

ECC Pipes

Tail pipes

Steam drums

Vertical Sectional View


BARCBARCBoiling water under natural circulation (i.e., no pumps are used in the main coolant circuit) cools the fuel clusters

Heat removal from core under both normal full power operating condition as well as shutdown condition is by natural circulation of coolant.


BARCBARC Even if the largest size pipe suddenly breaks, the Emergency Core Cooling System (ECCS) will flood the core with cold water, without any operator or control action

Passive injection of cooling water, initially from accumulator and later from the overhead GDWP, directly into fuel cluster.

(Th + Pu)O2

24 pins

(Th + U233)O2

30 pins

Water Tube

Displacer Rod


BARCBARC The reactor has unique advanced safety features to reliably cool it and shut it down even with human failure, power failure, and failure of all wired controls.

Pressure 70 bar

Pressure 71 bar

Pressure 76.5 barPressure 82 bar

Steam overpressure can passively shut down reactor


BARCBARC Computations indicate that the fuel temperature will hardly rise even with such extremely low probability accidents (contemplated in the design.)

Flow through Isolation Condenser Clad Surface Temperature


BARCBARC A large number of experimental facilities have been built and used to validate the computer codes used in AHWR design.

ISOLATIONCONDENSER

STEAM DRUM N2

CYLINDER

ADVANCEDACCUMULATOR

TAIL PIPE

GRAVITY DRIVENWATER POOL

RUPTURE DISC

HEADER

FEEDER

ECCS HEADER

FUEL CHANNEL SIMULATOR

INTEGRAL TEST LOOPINTEGRAL TEST LOOP


BARCBARC Some Thermal Hydraulic Experimental Facilities for Development of AHWR - 1/2

Facility at Apsara Reactor for Flow Pattern Transition Studies by Neutron Radiography

Natural Circulation Loop (NCL) for Stability and Start-up Studies


BARCBARC Some Thermal Hydraulic Experimental Facilities for Development of AHWR - 2/2

Transparent Set up for Natural Circulation Flow Distribution Studies

3 MW Boiling Water Loop


BARCBARC Most of the AHWR design objectives are consistent with the recent internationally stipulated requirements for next generation NPPs.

IAEA-TECDOC-1362, June 2003

This IAEA INPRO Report provides a Methodology for Assessment of Innovative Nuclear Energy Systems as based on the defined set of Basic Principles, User Requirements and Criteria in the areas of Economics, Sustainability and Environment, Safety, Waste Management, Proliferation Resistance and recommendations on Cross Cutting Issues.

AHWR was selected as the subject of a Case Study under INPRO. Its compliance with INPRO requirements was demonstrated in the Case Study report.


BARCBARC

The Indian Programme for Generation of Hydrogen using Nuclear Energy


BARCBARC Large scale commercial production of hydrogen is an energy intensive process


BARCBARC High temperatures (typically > 800 C) are generally required for efficiently producing hydrogen from water

Electrolysis

Thermo-chemical cycle

H2

Water

Electrolysis Processes:AW: Alkali Water, MC: Molten CarbonateSP: Solid Polymer, HT: High Temperature

Thermo-chemical Processes:Cu-Cl: Copper - Chlorine, Ca-Br2 : Calcium-Bromine, I-S: Iodine-Sulfur ProcessRef: High Efficiency Generation of HydrogenFuels Using Nuclear Power, G.E. Besenbruch, L.C. Brown, J.F. Funk, S.K. Showalter, Report GA–A23510 and ORNL Website

Ref: IAEA-TECDOC-1085: Hydrogen as an energy carrier and its production by nuclear power


BARCBARC

Comparison of thermo-chemical processes

I-S Process Ca-Br Process Cu-Cl Process

Efficiency (%) 57 40 41

Typical operating temperature

950oC 760oC 550oC

Process streams Liquid & gas Gas Liquid & gas

Development stage Fully flow sheeted

Fully flow sheeted

R&D stage

Demonstration Pre pilot plant

Pilot plant Not demonstrated

Corrosion High High Low

Capital Cost Low High -----


BARCBARC Schematic flow diagram of I-S process


BARCBARC BARC roadmap of R & D for the thermo-chemical process based hydrogen production

Demonstration using 600 MWTh HTR : ~ 80,000 m3 H2/hr

Demonstration with metallic chemical reactors :~ 13 m3 H2/hr

Lab scale demonstration : ~ 50 L H2/hr

Early R&D -Studies on reactions & separations

Experimental studies for improving specific processing methods

Evaluation &Development of materials

System design : Process, chemical reactors

FLOWSHEETING

Process simulation using chemical process simulator


BARCBARC High temperature electrolysis is more efficient and needs less electricity. For this process, nuclear reactors can supply both - high temperature heat & electricity.

High Temperature Steam Electrolysis (HTSE)

•A high temperature nuclear reactor coupled with a steam electrolyser would be extremely efficient with a thermal –to-hydrogen conversion efficiency of –55%

•Part of the energy needed to split the water is added as heat instead of electricity, thus reducing the overall energy required and improving process efficiency

•Super heated steam (at 850°C) is introduced at the cathode where hydrogen is separated and oxygen ion passes through a conducting ceramic membrane (usually Yttria Stabilized Zirconia, YSZ) and liberated at anode

•HTSE cell and components are similar to SOFC

•BARC is developing a 5 kW SOFC system

•SOFC development will ease switch over to steam electrolysis system

High Temperature Steam Electrolysis (Tubular

Geometry)


BARCBARC Nuclear hydrogen production system being developed in BARC is to satisfy total energy needs of a region in

the form of hydrogen, electricity and potable water

Turbo-Generator

Electricity

High Grade Heat

Desalination

Turbo-Generator

Conventional Nuclear Power Plant (Off-peak hour electricity)

High Temperature NuclearReactor for Combined Heat & Power Production

Electricity

Waste Heat

Solid Oxide Fuel CellOperating at 1000 °C

Electricity

Electricity

High GradeHeat

Hydrogen Storage

Hydrogen Fuel

Electrolysis Based Technologies

Hydrogen Production System

Reject Heat

Potable Water

Proton Exchange Membrane Fuel Cell

Automotive Applications

Thermo-Chemical Process

Hydrogen Fuel


BARCBARC A Compact High Temperature Reactor (CHTR) is under design at BARC. It will serve as the platform for developing and demonstrating technologies associated with Indian HTRs.

CHTR- Technology Demonstrator

•100 kWTh, 1000 °C, Portable, TRISO Fuel

•Several passive systems for reactor safety and heat removal - unattended operation

•Prolonged operation without refuelling

Multipurpose Nuclear Power Pack (MNPP)

•5 MWTh, 550 °C, Portable, Metallic Fuel

•Several passive systems for reactor safety and heat removal - unattended operation

•>15 year operation without refuelling

Indian HTR for Hydrogen Prodn.

•600 MWTh , ~1000 °C, TRISO

Fuel•Combination of active and

passive systems for control & cooling

•Medium life core


BARCBARC CHTR has an all ceramic core containing mainly BeO and carbon based components

Passive Power RegulationSystem

Molybdenum alloy Shell

Beryllia

Downcomers

Gas Gaps

High Thermal ConductivityMaterial Shells

Steel Shell

Graphite Reflector

Fuel Channels


BARCBARC Several innovations in the areas of fuel, materials, passive reactor safety, efficient heat removal systems & liquid heavy metal coolant technology mark CHTR configuration.

Heat Exchange Vessels

Gas Gap Filling

Upper Plenum

Lower Plenum

Shutdown System

System

Heat Pipes

50

Fuel ChannelBeryllia Moderator

Graphite Reflector

Passive Power

and Reflector

Regulation System

Major Design Guidelines

• Use of thorium basedfuels

• Passive core heat removalby natural circulation ofliquid heavy metalcoolant

• Passive power regulationand shutdownmechanism.

• Passive rejection of entireheat to the atmosphereunder accidentalcondition

• Compact design tominimise weight of thereactor


BARCBARC Passive systems for CHTR

Natural circulation of coolant

Passive regulation of reactor power under normal operation

Negative Doppler coefficient (-2.8 x 10-5 Δk/k/°C)

Negative moderator temperature coefficient

Passive shutdown for accidental conditions

Passive system for conduction of heat from reactor core by filling of gas gaps by liquid metal

Removal of heat from upper plenum, under both normal and accidental conditions by heat pipes

Removal of heat from the core by C/C composite heat pipes under accidental conditions with LOCA

Inherentl

y safe

Several of these features will be retained for the Indian High Temperature Reactor for Hydrogen production


BARCBARC Major Research & Development issues and critical

technologies for high temperature reactors

Materials related technologies• Molten heavy metal coolant technology - Experimental Loop being

set-up• Advanced TRISO coated fuel particles - Coating trials underway• BeO Production of required shape and size - Sample pieces made• Graphite & C-C composites for reactor components - Collaboration

with other R & D centre• High temperature structural materials - Under development• Oxidation and corrosion resistant coatings - Under development

Technologies for engineering systems• Passive reactor regulation & shutdown systems • High heat flux passive heat removal technologies • High temperature heat removal by heat pipes• Reactor physics calculations for compact cores - Codes developed• Structural and thermal design rules for brittle materials - Being

developed• High temperature instrumentation & components for liquid metals

- Being developed

Experimental set-up designed


BARCBARC Concluding Remarks

Indian Atomic Energy Programme has come of age.

The Programme has successfully delivered a self-reliant capability for its first stage involving setting up of Pressurised Heavy Water Reactor Systems and associated fuel cycle plants.

We have launched commercial Fast Breeder Reactor technology.

Our priority for the present and the future is to accelerate the development of the third stage, which would take us closer to our ultimate objective of exploitation of our vast thorium resources to address our long-term energy needs.


BARCBARC

Thank You


BARCBARC


BARCBARC The Indian energy resource position explains our strategy for deployment of nuclear energy

If the level of our per capita electricity consumption is raised to the level of a developed country (~5000 kWh/person/year) and only a single energy resource is to be used:

Domestic extractable coal reserves will last for < 13 years. Uranium in open cycle will last for ~ 0.5 year Uranium in closed cycle with FBRs will last for ~ 73 years Known reserves of thorium in closed cycle with

breeder reactors will last for > 250 years Entire renewable energy (including

hydroelectric capacity) will be sufficient for < 70 days/ year Total solar collection area (based on MNES estimate 20 MW/km2) needed will be at least ~ 31000 sq. km.

It is obvious that for long term energy security nuclear energy based on thorium has to be a prominent component of Indian energy mix.


BARCBARC Radiation is everywhere

Naturally occurring radiations due to indoor radon and radiation from outer space accounts for about 80% of our exposure, most of the balance is due to X-rays, air travel etc.

Source: Public myths and perception, DAE publication

TAPS RAPS MAPS NAPS KAPS KGS0

200

400

600

800

1000

1200

1400

Radiation dose due to one chest X-ray 400 Sv

Average background level 301 Sv / year in Lakshadwip

Average background level 1406 Sv / year in Kerala State

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Radiation Dose due to nuclear power at different NPP site boundary


BARCBARC The two conclusions of an Oak Ridge National Lab. Study

http://www.ornl.gov/ORNLReview/rev26-4/text/colmain.html

A typical 1000 MWe coal-fired plant

burns 4 million tons of coal each year Releases 5.2 tons of uranium (containing 74 pounds of

uranium-235) and 12.8 tons of thorium (Environmental Protection Agency figures – typical US coal contains uranium and thorium concentrations of 1.3 ppm and 3.2 ppm)

1. The energy content of nuclear fuel released in coal

combustion is 1.5 times more than that of the coal consumed.

2. Americans living near coal-fired power plants are exposed to higher radiation doses than those living near nuclear power plants that meet government regulations.


BARCBARC The volume of waste generated by nuclear power plant is very low. It can be stored for long period before disposal.

Waste generated from a 1000 MWe Coal fired power plant

Carbon dioxide : 2.6 million t /Year

Sulpher dioxide : 900 t /Year

NOx : 4500 t /Year

Ash : 3,20,000 t/Year

(with 400 t/Year of toxic heavy metals)

Waste generated from a 1000 MWe NPP

High Level : 35 t /Year

Intermediate Level : 310 t /Year

Low Level : 460 t /year

Solidified high level waste produced by generating electricity, for an average Indian family, for 25 years from nuclear power


BARCBARC A balanced perspective on accidents in energy industry (or any other industry serving society) is important.

The last serious accident in a nuclear reactor occurred about 18 years back which had tightened plant safety criteria

Three Mile Island (1979) No death toll Radiation was contained and there were no adverse

health or environmental consequences

Chernobyl (1986) 31 fatalities during fire fighting

8/14/2015 11:50 pm 2005-05-27 (delhi, petrofed) rks - india's energy security - the role of...

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