Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA...
Transcript of Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA...
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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
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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 2
The ITER Fuel Cycle is a unique fusion fuelling system.
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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 3
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
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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 4
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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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 5
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
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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 6
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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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 7
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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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 9
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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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 10
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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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 13
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