Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA...

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This information is private and confidential. © June 22, 2010 Review of the ITER Fuel Cycle Systems David Babineau, 23 rd IAEA FEC, 2010. Page 1 David Babineau David Babineau ITER Fuel Cycle Engineering Division ITER Fuel Cycle Engineering Division Tritium Plant Section Tritium Plant Section And And M. Glugla M. Glugla 1 1 , S. Maruyama , S. Maruyama 1 1 , R. Pearce , R. Pearce 1 1 , Li Bo , Li Bo 2 2 , B. Rogers , B. Rogers 3 3 , S. Willms , S. Willms 4 4 , , G. Piazza G. Piazza 5 5 , T. Yamanishi , T. Yamanishi 6 6 , S. H. Yun , S. H. Yun 7, 7, L. Worth L. Worth 1 1 and W. Shu and W. Shu 1 1 1 1 ITER Organization, Cadarache, France ITER Organization, Cadarache, France , , 2 2 Southwest Institute of Physics, Chengdu, China Southwest Institute of Physics, Chengdu, China , , 3 3 Savannah Savannah River National Laboratory, Aiken, SC USA River National Laboratory, Aiken, SC USA , , 4 4 Los Alamos National Laboratory, Los Alamos, NM, USA Los Alamos National Laboratory, Los Alamos, NM, USA , , 5 5 Fusion for Energy, Barcelona, Spain Fusion for Energy, Barcelona, Spain , , 6 6 JAEA, Directorates of Fusion Energy Research, Shirakata JAEA, Directorates of Fusion Energy Research, Shirakata - - Shirane, Shirane, Tokai, Ibaraki, Japan Tokai, Ibaraki, Japan , , 7 7 National Fusion Research Institute, Daejeon, Korea National Fusion Research Institute, Daejeon, Korea Review of the ITER Fuel Cycle Review of the ITER Fuel Cycle

Transcript of Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA...

Page 1: Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 15 Conclusions and Summary •ITER Fuel Cycle systems constitute a

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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 1

David BabineauDavid BabineauITER Fuel Cycle Engineering Division ITER Fuel Cycle Engineering Division

Tritium Plant SectionTritium Plant Section

AndAnd

M. GluglaM. Glugla11, S. Maruyama, S. Maruyama11, R. Pearce, R. Pearce11, Li Bo, Li Bo22, B. Rogers, B. Rogers33, S. Willms, S. Willms44, , G. PiazzaG. Piazza55, T. Yamanishi, T. Yamanishi66, S. H. Yun, S. H. Yun7, 7, L. WorthL. Worth11 and W. Shuand W. Shu11

11ITER Organization, Cadarache, FranceITER Organization, Cadarache, France, , 22Southwest Institute of Physics, Chengdu, ChinaSouthwest Institute of Physics, Chengdu, China, , 33Savannah Savannah River National Laboratory, Aiken, SC USARiver National Laboratory, Aiken, SC USA, , 44Los Alamos National Laboratory, Los Alamos, NM, USALos Alamos National Laboratory, Los Alamos, NM, USA, , 55Fusion for Energy, Barcelona, SpainFusion for Energy, Barcelona, Spain, , 66JAEA, Directorates of Fusion Energy Research, ShirakataJAEA, Directorates of Fusion Energy Research, Shirakata--Shirane, Shirane, Tokai, Ibaraki, JapanTokai, Ibaraki, Japan, , 77National Fusion Research Institute, Daejeon, KoreaNational Fusion Research Institute, Daejeon, Korea

Review of the ITER Fuel CycleReview of the ITER Fuel Cycle

Page 2: Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 15 Conclusions and Summary •ITER Fuel Cycle systems constitute a

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The ITER Fuel Cycle is a unique fusion fuelling system.

Page 3: Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 15 Conclusions and Summary •ITER Fuel Cycle systems constitute a

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Tritium (T) in ITER• With ITER, tritium handling and processing technology becomes anintegral part of the fusion program.

– ITER is a Nuclear Facility (4 kg tritium)• Employing DT as fusion fuel has positive effects

– Alpha heating of the plasma– Fusion reaction provides energy

• And it also introduces challenges– Primary tritium process systems – Auxiliary systems necessary

for the safe handling of tritium– Multiple barriers vital for

DT confinement in itsrespective process components

• ITER Tritium Plant is needed for deuterium-tritium fuel processing

Page 4: Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 15 Conclusions and Summary •ITER Fuel Cycle systems constitute a

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Tritium Plant Building Systems Layout• 7 Floors

– 2 belowgrade

• L = 80 m• W = 25 m• H = 35 m• Releasepoint elevation:60 m

– Tokamak building height: 57 m

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Select Fuel Cycle Requirements• Fuelling rates and torus pumping requirements different for inductive (450 s), for hybrid (1000 s) or for steady state (3000 s) operation

– 200 Pam3s-1 D-T, 160 Pam3s-1 D-T, 120 Pam3s-1 D-T, respectively• Tritium flow rate up to 50% of nominal fuelling rate (tritium purity 90%) • Deuterium flow rate up to 100% of nominal fuelling rate• Peak flow rate for both deuterium & tritium up to 200% of nominal fuelling rate

• Fuelling system transfer lines operated at sub-atmospheric pressures– Reliable confinement of tritium in transfer lines

• Line breach can be detected by a pressure rise• Pressure drop in pressurized line could have been leak or increasing demand

Page 6: Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 15 Conclusions and Summary •ITER Fuel Cycle systems constitute a

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Selected Fuel Cycle Requirements (cont.)• Widely distributed Vacuum Systems

– Cryo-Pumps, Roughing Pumps and Leak Detection / Localization• Service vacuum system, diagnostics, cryogenic guard vacuum

– Transfer of gases to Tritium Plant for processing• Tritium Plant for storage, supply, gas processing, isotope separation, tritium confinement / controlled discharge

– Safe and secured operation of hydrogen isotope inventories• Tritium accountancy and tracking

– Minimization of effluents and releases – 0.6 gram/year licensed (222 TBq = 6000 curies = 2.2 LiterSTP T2 )

• Ventilation 300 x 103 m3/hour – 2.63 x 1012 Liters per year

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Block Diagram of the ITER DT Fuel Cycle

Torus

Cryostat Cryo Pumps

Fuelling Gas Distribution

Pellet Injection

Neutral Beam Injection

Neutral Beam Cryo Pumps

Roughing Pumps

Isotope Separation

Storage and Delivery

Tokamak Exhaust Processing

Analytical System

Detritiation System

Water Detritiation

Tritium Depot

Torus Cryo Pumps

Disruption Mitigation System Gas Puffing

Leak Detection

Service Vacuum Systems

Glow DischargeCleaning

Hydrogen (Protium) Release

Off Gas Release

Fusion Power Shutdown System

Automated Control System, Interlock System, Security

KO, FUND

EU, FUND

JA, FUND

KO, FUND

EU, FUND

US, FUND

FUND

EU, FUND

US, FUND

CN,FUND

EU, JA, IN

EU, FUND

US FUNDEU, FUND

EU, FUND

CN, FUND

EU, FUND

Cryostat

FUND

CN, FUND

CN, FUNDTBD

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The ITER Closed Tritium Deuterium LoopTritium (T2)

Deuterium (D2)Storage

Tritium (T2)Deuterium (D2)

Fuelling

Plasma Isotope Separation

Pumping andExhaust

Processing

HTO, CT4, …He, N2, CO, CO2, …T2, D2, H2, DT, HT, HD

He, N2, CO, CO2, …H2O, CH4, ...

T2, D2 T2, D2

DT, HT, HD,T2, D2, H2

> 100 kg tritium per year20,000 $ per g> 1 billion €

< 2 kg tritium per yearburned in ITER

Tritiumrecyclingwith τ1

Tritium (T2)Deuterium (D2)

Storage

Tritium (T2)Deuterium (D2)

Fuelling

Detritiation SystemsPlasma Isotope

Separation

Pumping andExhaust

Processing

HTO, CT4, …He, N2, CO, CO2, …T2, D2, H2, DT, HT, HD

He, N2, CO, CO2, …H2O, CH4, ...

T2, D2 T2, D2

DT, HT, HD,T2, D2, H2

Tritium (T2)Deuterium (D2)

Storage

Tritium (T2)Deuterium (D2)

Fuelling

Detritiation SystemsPlasma Isotope

Separation

Water-Detritiation

Isotope SeparationPumping and

Exhaust Processing

HTO, CT4, …He, N2, CO, CO2, …T2, D2, H2, DT, HT, HD

He, N2, CO, CO2, …H2O, CH4, ...

DT, HT

H2,HD

T2, D2 T2, D2

DT, HT, HD,T2, D2, H2

H2, D2, HD, O2

H2O, HDO, HTO

DT, HT

Tritiumrecyclingwith τ2

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Tritium Confinement for ITER Nuclear Buildings • Confinement of tritium within Fuel Cycle processing systems and components is the most important safety objective

– Basic targets of confinement• Prevent spreading of radioactive material in normal operation• Keep radiological consequences in off-normal conditions within acceptable

levels– Confinement function is achieved by a coherent set of physical barriersand / or auxiliary techniques

• First confinement system designed to prevent releases of radioactive materials into the accessible working areas

• Second confinement system prevents releasesto general public and the environment

– ISO 17873 provides criteria for design & operation of ventilation systems (HVAC) for nuclear installations other than nuclear reactors

• ISO 17873 was transposed for ITER to include gaseous tritium and tritiated compounds as airborne contaminants

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First Confinement Safety• Example - Storage and Delivery - Jacketed Vessels, Uranium Hydride Storage

GB-y-3x00y-3x02

y-3x91 y-3x90TIR

FIR

FIRCA±

FIRy-3x01

y-3x00

y-3x92

PIRA+S++

TIR

to SafetyBuffer VesselTritium Supply to

Tokamak

He CalorimetryLoop

Tritium fromIsotope Separation He

Supply

HighVacuum

0

1

2

3

4

5

6

7

0,5 1 1,5 2 2,5 3 3,5

log P

H2 (P

a)

1000/T (K)

727 394 227 127 60Temperature (°C)

UH3TiH

ZrH

YH

YH2

ZrCoH2

UH3

LaNi5H

4

ZrNiH2

decomposition pressure equals atmospheric pressure

ZrCo hydridestarts to release H

2(150°C)

Uranium hydridestarts to release H

2(250°C)after disprop.

(550°C)

Van‘t Hoff Diagram for Various HydridesTypical Hydride Bed

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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 11

ITER Ventilation & Confinement Concept• Pressure Cascade• First confinement system caninclude more than one barrier

– Nitrogen filled Glove box – Glovebox atmosphere detritiation

• Second confinement systemcomprises sub-atmosphericpressure control andatmosphere detritiation

– Heating, Ventilation,Atmosphere Conditioning(HVAC)

– Vent detritiation

Glove box

VDS

HVAC HVAC

Tritium System

Room

Purge gasN2

GDS

Glove box

Tritium Spill

Second Confinement Safety

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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 12

ITER Detritiation System Block Diagram

• Detritiation System is based on oxidation of tritium to water followed by molecular sieve bed driers or wet scrubber columns

Second Confinement

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Wet Scrubber Column for Air DetritiationH2O; (LH2O) Decontaminated air; (G)

to stack

Tritiated water, HTO; (LHTO) Contaminated air; (G)

Counter-flow isotopic exchange in packed columnHTOV + H2OL� H2OV + HTOL

StructuredPacking

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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 14

Water Detritiation

• Confinement philosophy utilizing a combinationof Isotope Separation with Water Detritiationsystem (WDS)

– No tritium primary processingsystem dischargesdirectly to environment

Liquid PhaseCatalytic Exchange

ColumnITERCryogenicDistillationColumn 1

Ef ~103-104

HTO:1 mCi/kg - 10 Ci/kg

H2 To Stack

IsotopeSeparation

SystemElectrolyzer

H2, HD, HT,H2OTritiated

waterfeed

Fresh water supply

Permeator

H2, HD, HT

H2, (HD, HT)

Purifier

H2, D2, HD, O2 To Stack

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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 15

Conclusions and Summary• ITER Fuel Cycle systems constitute a rather complex chemical plant

– Unprecedented high throughputs of tritium - largest tritium plant in the world

– Complex Fuelling and Vacuum Systems with many interfaces– Tritium Plant with closed loop tritium processing systems

• Tritium confinement, safety and security– Control of effluents and release– Solid concept to handle this currently in Detailed Design phase