U.S. Department of Energy Advanced Reactor Research and Development Program for Fast Reactors

Transcription

1 資料 1 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

2 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

3 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 10 th Executive Order Promoting Energy Independence and Economic Growth Commercialization of advanced SMRs crucial to future of US nuclear sector 3

4 DOE-NE MISSION AND PRIORITIES 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. RD&D INFRASTRUCTURE MISSION PRIORITIES Existing Fleet Advanced Reactor Pipeline Fuel Cycle Infrastructure TREAT VTR LWR LIFE EXTENSION (80 yrs) LWR LIFE EXTENSION (60 yrs) USED FUEL STORAGE ADVANCED REACTORS NUCLEAR HYBRID ENERGY ADVANCED LWR FUELS SMALL MODULAR REACTORS SUSTAINABLE FUEL CYCLE GEOLOGIC REPOSITORY 4

5 DOE-NE ADVANCED REACTORS PIPELINE REACTOR TYPES 12 X 50 MWe 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 Xe-100 Pebble-Bed Reactor (200 MWth) AREVA - HTGR 5

6 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 GE PRISM (840 MWth, 311 MWe)) GA EM 2 (265 MWe) Transportable Microreactors (~5 MWth) TerraPower TWR (550 MWe) 6

7 ADVANCED REACTOR EXAMPLES Different Advanced Reactor Designs Being Developed By Industry Gas Reactors Fast Reactors GA Gas-cooled Fast Reactor GE Hitachi PRISM Molten Salt Reactors TerraPower TWR Advanced Reactor Concepts LLC ARC-100 TerraPower MCFR Elysium USA MCSFR 7

8 WHAT IS GAIN INITIATIVE? Gateway for Accelerated Innovation in Nuclear What are the issues? What do we need to do? What is the DOE initiative? 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. 8

9 GAIN: Connecting nuclear innovators to DOE laboratory capabilities and RD&D programs Modeling & Simulation Crosscutting Design Support NRC Interface Base 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 Modeling and Simulation Expertise Unique Facilities Knowledge Management & Integration Industry and investor access to DOE capabilities and expertise gain.inl.gov 9

10 DOE-NE FAST REACTOR PROGRAM OBJECTIVES 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 INFRASTRUCTURE e.g. Test Reactors DATA & KNOWLEDGE MANAGEMENT TRAINING OF NEXT GENERATION OF ENGINEERS & SCIENTISTS INTERNATIONAL COLLABORATIONS 10

11 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. Experimental Breeder Reactor (EBR-II) Fast Flux Test Reactor (FFTF) 11

12 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

13 DRAFT REQUIREMENTS/ASSUMPTIONS OF VERSATILE TEST REACTOR (VTR) 1. Approach to Design: Conducting a 3 year research & development effort on core design. 2. Reach fast flux of approximately 4.E15 n/cm 2 -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 4

14 PRELIMINARY VTR SIZING STUDIES 3 14

15 FUEL OPTIONS FOR VTR Fuel Composition Peak Fast Neutron Flux n/cm 2 -s 300 MW VTR* Fuel Current TRL Annual HM Requirement U-20Pu-10Zr with 5% 235 U (BASELINE) U-27Pu-10Zr with depleted or natural U U-10Zr with ~20% 235 U ~ High 330 kg/y Pu and 1170 kg/y U with 5% 235 U ~ Low 450 kg/y Pu and 1050 kg/y U ~ High 1500 kg/yr of U with ~20% 235 U *Calculations are based assuming typical isotopic composition for reactor grade Pu 15

16 TREAT UPDATE Achieved criticality on November 14, Calibration and start-up testing continues Test vehicles are being developed for transient testing of multiple fuel types in the next few years. 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 16

17 POOL vs. LOOP DESIGNS FOR SODIUM-COOLED FAST REACTORS LOOP DESIGN Primary pumps and intermediate heat exchanges are outside the vessel More compact design with potential cost savings POOL DESIGN Primary pumps and intermediate heat exchanges are inside the vessel 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 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. 17

18 OXIDE vs. METALLIC FUELS FOR SODIUM-COOLED FAST REACTORS Fast Reactor Fuel Type Fresh Fuel Properties Metal U-20Pu-10Zr Oxide UO 2-20PuO 2 Heavy Metal Density, g/cm Melting Temperature, ºK Thermal Conductivity, W/cm-ºK Operating Centerline Temperature at 40 kw/m, ºK, and (T/T melt ) 1060 (0.8) 2360 (0.8) Fuel-Cladding Solidus, ºK Thermal Expansion, 1/ºK 17E-6 12E-6 Heat Capacity, J/gºK Reactor Experience, Country Research & Testing, Country US, UK US, JAP, ROK, CHI RUS, FR, JAP US, UK RUS, FR, JAP, US, CHI 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 + electrochemical processing for closing the fuel cycle. 18

19 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

20 Back Up Slide

21 NE ORGANIZATION Office of Human Capital & Business Services Chief Operating Officer Office of Budget & Planning NE-1/2 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 Staff Nuclear Energy Advisory Committee Chief Technology Officer NE-3 NE-4 NE-5 NE-6 NE-7 NE-8 Deputy Assistant Secretary for Nuclear Infrastructure Programs Deputy Assistant Secretary for Nuclear Technology Research and Development Deputy Assistant Secretary for Nuclear Energy Innovation and Application Deputy Assistant Secretary for International Nuclear Energy Policy and Cooperation Manager, Idaho Operation Office Deputy Assistant Secretary for Spent Fuel & Waste Disposition Office of Nuclear Facilities Management Office of Advanced Reactor Technologies Office of Accelerated Innovation in Nuclear Energy Office of Bilateral, Multilateral and Commercial Cooperation Office of Spent Fuel and Waste Science and Technology Office of Nuclear Materials Production, Management & Protection Office of Advanced Fuels Technologies Office of Materials and Chemical Technologies Office of Nuclear Energy Application Office of International Nuclear Safety Office of Integrated Waste Management Office of Program Operations