大洗 2007年 4月 日16-19 Slide 1 Matt Richards, Arkal Shenoy, and Mike Campbell – General Atomics IAEA International Conference on Non-Electric Applications of Nuclear Energy Japan Atomic Energy Agency Oarai, Japan April 16-19, 2007 Matt Richards General Atomics, San Diego, CA, USA (JAEA Oarai Research Center) [email protected]Pre-Conceptual Hydrogen Production Modular Helium Reactor Designs
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大洗 2007年 4月 日16-19 Slide 1
Matt Richards, Arkal Shenoy, and Mike Campbell – General Atomics
IAEA International Conference on Non-Electric Applications of Nuclear Energy
Electricity costs result mostly from pumping process fluids in the hydrogen plant (not from pumping helium). Efforts are being made to optimize the flow sheets to reduce pumping requirements.
SOE module unit costs assumed to be $500/kW(e). If module unit costs are increased to $1000/kW(e), hydrogen production cost increased to $2.52/kg.
大洗 2007年 4月 日16-19 Slide 11
Nuclear Hydrogen Production Costs Compare Favorably with Steam-Methane Reforming
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0.50
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2.00
2.50
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0 2 4 6 8 10 12 14 16 18 20Price of Natural Gas ($/MMBtu)
Cos
t of H
ydro
gen
($/k
g)
SMR - No CO2 Penalty
SMR - $30/mt CO2 Penalty
SMR - $50/mt CO2 Penalty
Nuclear Hydrogen, $1.97/kg
Nuclear Hydrogen with $20/mt O2Credit, $1.81/kg
$9.72/MMBTUDecember 2005 Natural Gas Wellhead Price
Economic comparisons are especially favorable if carbon dioxide penalties and oxygen credits are taken into account.
大洗 2007年 4月 日16-19 Slide 12
VHTR Can Provide a Wide Variety of Energy Outputs
Electricity
Steam
Process Heat
Hydrogen
NaturalGas
Coal Gasification
大洗 2007年 4月 日16-19 Slide 13
GT-MHRs and H2-MHRs Can Be Deployed with Advanced Fuel Cycles to Address Spent Fuel Management and Sustainability Issues
LWR
Spe
nt F
uel
Deep Burn using MHRs fully fueled with TRU
Pu-239 burnup > 95 %
All-Actinides burnup > 60 %
Np-237 and Precursors > 60 %
Pu-239 burnup > 95 %
All-Actinides burnup > 60 %
Np-237 and Precursors > 60 %
Waste accumulation 75 kgTRU /GWe-yr
UREX
Fission Products
TRU
U recycle
MHRs can be used to process legacy LWR spent fuel
Residual radioactivity is contained by ceramiccoatings over geologic time scales
Pu Oxide (PuO1.68)
747,000 MW-days/tonne>95% 239Pu Transmuted at
Peach Bottom I
Successful Deep-Burn Irradiation of Coated-Particle Pu-Fuel
大洗 2007年 4月 日16-19 Slide 14
MHRs Can Be Deployed Using a Self-Cleaning Fuel Cycle to Relieve Repository Burdens
TRISO FAB
Pu, Transuranics
LEU (15-20%)
UREXFP
Ura
nium
Waste accumulation: 35 kgTRU /GWe-yr8 times less than present LWRs
EURANIUM
DB-TRISO FAB
Sustainability: 200 – 300 years in U.S.
大洗 2007年 4月 日16-19 Slide 15
FBR/VHTR System Deployment Provides Sustainability, Proliferation Resistance, and Energy Flexibility
SFR
VHTRFuel
Manufacturing
Depleted Uranium
1
2SFR Core
FuelManufacturing
SFR BlanketFuel
Manufacturing
4
5
VHTR
16
26Loss
Loss25
Loss24
Core
6
7Blanket
8SFR
Spent FuelStorage
9SFR
Front EndReprocessing
22Loss
VHTRSpent Fuel
Storage17 18
VHTRFront End
Reprocessing
23Loss
SpentFuel
Reprocessing
10
19
Seperations11
Heavy MetalStorage
Heavy MetalStorage
12
14
28
27
21
U
FPs
UnrecycledCm
20
Loss
Recycled Uranium
LWR Pu+ MA
LWR Pu+ MA
15
3
13
VHTROnce-Through
Option
Deep BurnFuel Cycle.Generate degraded TRU to spike SFR Blanket.
Long-term sustainability for resource-deficient countries (e.g., Japan)
JAEA/GA jointly investigating FBR/VHTR deployment scenarios in Japan.
大洗 2007年 4月 日16-19 Slide 16
Conclusions
• MHR design features make it an outstanding choice for future deployment of nuclear energy– Passive safety– High-temperature capability– High thermal efficiency, flexible siting– Flexible fuel cycles and energy outputs
• MHR deployment supports significant, sustainable expansion of nuclear energy– Better utilization of repository space with greatly
reduced requirements for recycle of nuclear fuel– Deployment in symbiosis with FBRs can provide virtually