U.S. Department of Energy Advanced Reactor
Research and Development Program for Fast
Reactors
John W. Herczeg
Deputy Assistant Secretary
for Nuclear Technology Research and Development
Office of Nuclear Energy
March 1, 2018
資料1
PRESENTATION OUTLINE
DOE-NE MISSION AND PRIORITIES
DOE-NE ADVANCED REACTORS PIPELINE
INDUSTRIAL FAST REACTOR INITIATIVES
GAIN INITIATIVE
SODIUM-COOLED FAST REACTORS
WHY A FAST SPECTRUM TEST REACTOR
VERSATILE TEST REACTOR DESCRIPTION
TREAT UPDATE
POOL vs. LOOP REACTORS
METAL vs. OXIDE FUELS
CONCLUSIONS
2
Presidential and Departmental Nuclear Energy Priorities
• President Trump ordered review of nuclear energy policy:
“[W]e will begin to revive and expand our nuclear energy sector…which produces clean, renewable and emissions-free energy. A complete review of U.S. nuclear energy policy will help us find new ways to revitalize this crucial energy resource.”
• Nuclear energy role as clean baseload power is key to environmental challenges:
“If you really care about this environment that we live in…then you need to be a supporter of this amazingly clean, resilient, safe, reliable source of energy.” Secretary Rick Perry at Press conference, May 10th
• Executive Order Promoting Energy Independence and Economic Growth
• Commercialization of advanced SMRs crucial to future of US nuclear sector
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MISSION PRIORITIES
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2010 20202030 2040
LWR LIFE EXTENSION (60 yrs)USED FUEL STORAGE
ADVANCED LWR FUELSSMALL MODULAR REACTORS
ADVANCED REACTORS NUCLEAR HYBRID ENERGYLWR LIFE EXTENSION (80 yrs)
SUSTAINABLE FUEL CYCLEGEOLOGIC REPOSITORY
TREAT VTR
RD&D INFRASTRUCTURE
DOE-NE MISSION
• Advance nuclear power as a resource capable of making major contributions in meeting our Nation’s energy supply, environmental and energy security needs
• Seek to resolve technical, cost, safety security, and regulatory issues through RD&D
• By focusing on the development of advanced nuclear technologies, support the goals of providing domestic sources of secure energy, reducing greenhouse gases, and enhancing national security.
Existing Fleet
Advanced Reactor Pipeline
Fuel Cycle Infrastructure
DOE-NE MISSION AND PRIORITIES
REACTOR TYPES
Light-Water Based SMRs
e.g. NuScale
High-Temperature Reactors
• Prismatic & pebble bed designs
• Helium Cooled
• Molten Salt Cooled
Emphasis: TRISO fuel and Graphite qualification
Liquid Fueled Reactor (Molten Salt)
• Fast-, thermal- and hybrid-spectrum designs
Fast Spectrum Reactors
• See next viewgraph
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Xe-100 Pebble-Bed Reactor (200 MWth)
AREVA - HTGR
12 X 50 MWe
DOE-NE ADVANCED REACTORS PIPELINE
INDUSTRIAL FAST REACTOR INITIATIVES
REACTOR TYPES
Sodium-Cooled
e.g. TerraPower TWR, GE PRISM, ARC-100
Lead or Lead-Bismuth Eutectic-Cooled
e.g. Westinghouse (Lead), Gen4Energy (LBE)
Gas-Cooled
e.g. GA EM2
Molten Salt-Fueled
e.g. TerraPower MCFR, Elysium MCSFR
Heat-Pipe Cooled Microreactors
e.g. OKLO, Westinghouse
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GA EM2 (265 MWe)
GE PRISM (840 MWth, 311 MWe))
TerraPower TWR (550 MWe)
Transportable Microreactors (~5 MWth)
Different Advanced Reactor Designs Being Developed By Industry
Gas Reactors
GE HitachiPRISM
TerraPowerTWR
Advanced Reactor Concepts LLC
ARC-100
Fast Reactors
Molten Salt
Reactors
Elysium USAMCSFR
TerraPowerMCFR
GA Gas-cooled Fast Reactor
ADVANCED REACTOR EXAMPLES
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WHAT IS GAIN INITIATIVE?
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• Time to market is too long
• Facilities needed for RD&D are expensive
• Capabilities at government sites have not been easily accessible
• Technology readiness levels vary
• Some innovators require assistance with regulatory processes
• Provide nuclear innovators and investors with single point of access into DOE complex
• Provide focused research opportunities and dedicated industry engagement
• Expand upon DOE’s work with Nuclear Regulatory Commission (NRC)
• Private-public partnership, dedicated to accelerating innovative nuclear energy technologies time to market
DOE recognizes the magnitude of the need, the associated sense of urgency and the benefits of a strong and agile private-public partnership in achieving the national goals.
What are the issues?
What do we need to do?
What is the DOE initiative?
Gateway for Accelerated Innovation in Nuclear
GAIN:
9@GAINnuclear
Modeling and Simulation
Knowledge Management & Integration
Unique Facilities
Modeling & Simulation
Crosscutting Design Support
NRC InterfaceBase Reactor
and Fuel Cycle R&D Programs
Experimentation
HPC Infrastructure
Verification and Validation
M&S Expertise
Reactor physics
Nuclear Hybrid Energy
Nuclear Cyber Security
Digital I&C Human Factors
Licensing Framework
Gradual Risk Reduction
Licensing Support Expertise
Advanced Fuel Cycles
Advanced Reactors
LW-based Reactors
Nuclear Fuels
Instrumentation and Sensors
Materials Science
Test Reactors
– GAIN –
Industry and investor access to DOE capabilities and expertise
Expertise
gain.inl.gov
Connecting nuclear innovators to DOE laboratory capabilities and RD&D programs
DOE-NE FAST REACTOR PROGRAM OBJECTIVES
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• For fast reactor commercial deployment, two recurring challenges are identified
• Capital cost
• Licensing framework for non-LWRs
• Capital cost reduction through application of innovative technology solutions
• Improved design approach – components and maintenance
• Advanced materials
• Advanced energy conversion to improve size/efficiency
• Advanced modeling and simulation to optimize performance
• Fuel development to improve fuel cycle costs
• Resolution of key licensing issues
• Safety R&D to validate tools and assure margins
• Qualification of fast reactor fuels
R&D INFRASTRUCTUREe.g. Test Reactors
DATA & KNOWLEDGE MANAGEMENT
TRAINING OF NEXT GENERATION OF ENGINEERS
& SCIENTISTS
INTERNATIONAL COLLABORATIONS
WHY SODIUM FAST REACTORS?
• U.S. and global experience with sodium-cooled fast reactors (SFR) is more mature compared to other types of fast reactors.
• SFR is ready for prototyping/demonstration
• However, it is not clear that today’s design combined with today’s technologies will meet the requirements for capital, operational and fuel-cycle costs.
• Commercial market readiness, including supply-chain and human capital, is an issue.
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Experimental Breeder Reactor (EBR-II)
Fast Flux Test Reactor (FFTF)
WHY A TEST REACTOR?
• Innovative technologies are being pursued to reduce capital, operations, and fuel-cycle costs for the next generation of sodium-cooled fast reactors.• Higher burnup fuels
• Metallic fuels without sodium bonding
• Materials that can sustain much higher dpa (400 dpa!!)
• Other fast reactor designs being pursued by industry (lead, LBE, gas, molten salt) rely on different fuel and material types.• Commercial viability and licensing requires considerably more data
• For sustaining long-term commercial fast reactor operations, a test reactor is needed for continuous technology improvements.• We are still conducting tests for LWR fuels and materials in test reactors.
• It took decades to go from 60% to 90+% availability in LWRs partly because of continuous improvements in fuels and materials.
• Globally, access to fast spectrum irradiation capabilities for general purposes is very limited (only exists in Russian Federation today). 12
1. Approach to Design: Conducting a 3 year research & development effort on core design.
2. Reach fast flux of approximately 4.E15 n/cm2-s, with prototypical spectrum
3. Load factor: as large as possible (maximize dpa/year to > 30 dpa/year)
4. Provide flexibility for novel experimental techniques
5. Be capable of running loops representative of typical fast reactors (Candidate Coolants: Na, Lead, LBE, Gas, Molten Salt) – May be a single location with replaceable loops.
6. Effective testing height ≤ 1 m
7. Ability to perform large number of experiments simultaneously
8. Metallic driver fuel (possible options: LEU, Pu, LEU+Pu) 13
DRAFT REQUIREMENTS/ASSUMPTIONS
4
OF VERSATILE TEST REACTOR (VTR)
FUEL OPTIONS FOR VTR
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Fuel
Composition
Peak Fast Neutron
Flux n/cm2-s
300 MW VTR*
Fuel
Current TRL
Annual HM
Requirement
U-20Pu-10Zr
with 5% 235U
(BASELINE)
~ 4.5×1015 High 330 kg/y Pu and
1170 kg/y U
with 5% 235U
U-27Pu-10Zr
with depleted or
natural U
~ 5.0×1015 Low 450 kg/y Pu and
1050 kg/y U
U-10Zr with
~20% 235U
~ 2.5×1015 High 1500 kg/yr of U
with ~20% 235U
*Calculations are based assuming typical isotopic composition for reactor grade Pu
TREAT UPDATE
• Achieved criticality on November 14, 2017.
• Calibration and start-up testing continues
• Test vehicles are being developed for transient testing of multiple fuel types in the next few years.
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• Over 20 GW Peak Transient Power (120 kW Steady-state power)
• Core: Height (4 feet); Diameter (about 6 feet); surrounded by 2 feet graphite reflector
• Fuel: 19 x 19 array (approximately 360 fuel elements) of 4 inch X 4 inch fuel and reflector assemblies
POOL vs. LOOP DESIGNS FOR SODIUM-COOLED FAST REACTORS
LOOP DESIGN POOL DESIGN
Primary pumps and intermediate
heat exchanges are outside the
vessel
Primary pumps and intermediate
heat exchanges are inside the vessel
More compact design – with
potential cost savings
Larger vessel
Potential Safety Benefits:
• Higher sodium thermal inertia –
smoother response to transients
• No vessel penetrations
• No LOCA as a result of a leak
• Radioactive materials
confinement
• Decay heat removal reliability
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Based on previous experience, U.S. prefers the the pool design. However, either
design can be made to work with equivalent safety by proper engineering design.
OXIDE vs. METALLIC FUELS FOR SODIUM-COOLED FAST REACTORS
• U.S. has considerable experience with both metallic alloy and mixed oxide fuels for SFRs
• Both fuel types can meet the safety and performance requirements
• U.S. prefers metallic alloy fuels for additional operational and safety margins based on:
• Extensive data collected in EBR-II, FFTF and TREAT
• Preferred behavior during clad breach and fuel dispersal experiments conducted in TREAT
• Metallic fuel behavior and negative reactivity feedback during unprotected accidents
• Loss-of-flow• Loss-of heat sink
• Metallic fuel + electro-chemical processing for closing the fuel cycle.
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Fast Reactor Fuel Type
Fresh Fuel Properties
Metal
U-20Pu-10Zr
Oxide
UO2-20PuO2
Heavy Metal Density, g/cm3 14.1 9.3
Melting Temperature, ºK 1350 3000
Thermal Conductivity, W/cm-ºK 0.16 0.023
Operating Centerline
Temperature
at 40 kW/m, ºK, and (T/Tmelt)
1060
(0.8)
2360
(0.8)
Fuel-Cladding Solidus, ºK 1000 1675
Thermal Expansion, 1/ºK 17E-6 12E-6
Heat Capacity, J/gºK 0.17 0.34
Reactor Experience, Country US, UKRUS, FR, JAP
US, UK
Research & Testing, CountryUS, JAP, ROK,
CHI
RUS, FR, JAP,
US, CHI
CONCLUSIONS
• Through private-public partnerships, the U.S. is exploring the possibility of rapidly deploying demonstration/prototype advanced reactors• The pace depends on availability of private and public investments,
customers (utilities) interest, and overcoming the financial and licensing risks
• The decision on the type of demonstration/prototype reactor must be based on commercial viability and guided by private sector and customers. Commercial viability depends on• Capital, operational and fuel cycle cost
• Passive safety features and ease of operations
• Supply-chain and human capital availability
• DOE-NE programs are supporting multiple design options through the ongoing R&D programs.
• In parallel, DOE-NE is also investing in the R&D infrastructures (with emphasis on the test reactor) to assure a sustainable fast-reactor industry in the long-run.• TREAT already restarted
• Versatile Test Reactor (VTR) targeted for availability by 2026
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Nuclear Energy Advisory
Committee
Deputy Assistant
Secretary for Nuclear
Infrastructure Programs
Deputy Assistant
Secretary for Nuclear
Technology Research and
Development
Manager, Idaho Operation
Office
Deputy Assistant
Secretary for International
Nuclear Energy Policy
and Cooperation
Deputy Assistant
Secretary for Spent Fuel
& Waste Disposition
Deputy Assistant
Secretary for Nuclear
Energy Innovation and
Application
Chief Operating Officer
Assistant Secretary for Nuclear Energy
Acting Assistant Secretary
Principal Deputy Assistant Secretary
Associate Principal Deputy Assistant Secretary
Central Technical Authority/Chief of Nuclear Safety
Senior Advisors
Chief of StaffChief Technology Officer
Office of Nuclear
Facilities Management
Office of Nuclear
Materials Production,
Management &
Protection
Office of Advanced
Fuels Technologies
Office of Advanced
Reactor Technologies
Office of Materials and
Chemical Technologies
Office of Accelerated
Innovation in Nuclear
Energy
Office of Nuclear
Energy Application
Office of Bilateral,
Multilateral and
Commercial Cooperation
Office of International
Nuclear Safety
Office of Spent Fuel and
Waste Science and
Technology
Office of Integrated
Waste Management
Office of Program
Operations
Office of Budget &
Planning
Office of Human
Capital & Business
Services
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NE ORGANIZATION