Global Nuclear Energy Partnership Technology Demonstration Program
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1 Global Nuclear Energy Partnership Technology Demonstration Program Dave Hill Deputy Director, Science and Technology Idaho National Laboratory August
2 Global Nuclear Energy Partnership Goals of GNEP: Expand domestic use of nuclear power; Demonstrate more proliferation-resistant recycling; Minimize nuclear waste; Develop advanced burner reactors; Establish reliable fuel cycle services; Demonstrate small-scale reactors; Develop enhanced nuclear safeguards. 2
3 Global Nuclear Energy Partnership Technology Demonstration (GNEP-TD) GNEP Technology Demonstration Program Focus on domestic demonstration of key technologies International partnerships in technology development Embedded university program 5-year technology plan under development 9 labs involved Provision of intellectual basis for GNEP-TD decisions Basis studies Office of Science is supporting nuclear technology through coordinated programs in BES (Chemistry, materials etc), Nuclear Physics and Comuptation 3
4 GNEP Technology Demonstration Facilities 4
5 GNEP-TD Facilities Engineering-Scale Demonstration (ESD) Demonstration of the UREX+1a process Source of supply of transuranic elements for Advanced Burner Test Reactor Suitable for process optimization Size is to be determined from performance requirements Advanced Burner Test Reactor (ABTR) Demonstrate performance of transmutation fuel Size is to be determined from performance requirements Advanced Fuel Cycle Facility (AFCF) Modular research laboratory Aqueous separations demonstration at up to 25 metric tons per year Pyrochemical separations demonstration at 1 metric ton per year Recycle fuel fabrication development and demonstration Supporting R&D laboratories 5
6 GNEP Separations Technology Development Two main program paths Management of the spent fuel generated by current generation LWRs and future ALWRs (ESD) Closure of the fuel cycle for advanced burner reactors (AFCF) Near term objective is dealing with the large amount of spent fuel generated by the current fleet of commercial power reactors Spent fuel generated at a rate of about 2,000 metric tons (heavy metal) per year Projected accumulation of commercial spent fuel will greatly exceed the legislated capacity of the Yucca Mountain repository by 2050 Goal is to preclude or significantly delay the need for a second geologic repository 6
7 Advanced Aqueous Processing of LWR Spent Fuel Aqueous solvent extraction process is the reference method being developed for treatment of LWR spent fuel High degree of technological maturity; industrial practice in France, the United Kingdom, Russia, and Japan Capable of achieving high decontamination factors for separated products For thermal recycle, must eliminate high cross section fission products nearly completely (DF>10,000 required) For fast reactor recycle, must reduce the rare earth content (DF>250 for separation of lanthanides from transuranics) Provides flexibility in degree of partitioning of radionuclides present in spent fuel Emphasis on group extraction of transuranics to confer a degree of proliferation resistance to the process Suite of process variants under development 7
8 Suite of UREX+ Processes Process Prod #1 Prod #2 Prod #3 Prod #4 Prod #5 Prod #6 Prod #7 UREX+1 U Tc Cs/Sr TRU+Ln FP UREX+1a U Tc Cs/Sr TRU All FP UREX+2 U Tc Cs/Sr Pu+Np Am+Cm+Ln FP UREX+3 U Tc Cs/Sr Pu+Np Am+Cm All FP UREX+4 U Tc Cs/Sr Pu+Np Am Cm All FP Notes: (1) in all cases, iodine is removed as an off-gas from the dissolution process. (2) processes are designed for the generation of no liquid high-level wastes U: uranium (removed in order to reduce the mass and volume of high-level waste) Tc: technetium (long-lived fission product, prime contributor to long-term dose at Yucca Mountain) Cs/Sr: cesium and strontium (primary short-term heat generators; repository impact) TRU: transuranic elements (Pu: plutonium, Np: neptunium, Am: americium, Cm: curium) Ln: lanthanide (rare earth) fission products FP: fission products other than cesium, strontium, technetium, iodine, and the lanthanides 8
9 Advanced Fuel Cycle Facility (AFCF) main mission is to develop and demonstrate advanced fuel recycling technologies Cost effective alternatives for high level nuclear waste management in the form of advanced closed fuel cycles. Advanced proliferation-resistant fuel recycling technologies including chemical processing and fuel fabrication. Advanced safeguards including advanced instrumentation for materials protection, control and accountability (MC&A), and advanced control and monitoring systems. Advanced Processing AFCF Advanced Fuel Fabrication Advanced Safeguards 9
10 AFCF is a multi-purpose facility for bench-scale to engineering-scale technology development & demonstration Remote fuel fabrication development and demonstration. Fabrication of transuranic (TRU) -bearing transmutation fuels at the rod and subassembly scale. Integrated aqueous process development and demonstrations of spent fuel treatment using Light Water Reactor (LWR) spent nuclear fuel (SNF). Integrated dry process development and demonstration of fast reactor (FR) spent fuel treatment. Development and proof-testing of advanced safeguards instrumentation and methodology. Process improvements, either in the form of new flow-sheets or advanced process equipment. Flexibility to facilitate the development and demonstration of recycling methods for advanced fuel types that can support a number of fuel cycle strategies. Advanced Processing AFCF Advanced Fuel Fabrication Advanced Safeguards Data on closed fuel cycle attributes: Economics Safety Non-proliferation Environmental 10
11 AFCF will contain multiple modules with hot-cells and shielded glove-boxes. Remote fuel fabrication module 8 LTA/yr Aqueous processing facility 25 ton/yr Pyroprocessing module 1 ton/yr R&D module: small-hot cells and shielded glove-boxes for bench-scale research. Research Module Aqueous process Module Pyroprocess Module Remote Fuel Fabrication Module Analytic Laboratory 11
12 Advanced Burner Test Reactor: A Key Component of GNEP-TD Thermal reactors only suited for limited transmutation: The role of thermal reactors for transmutation in the US is strongly reduced by the policy that avoids separation of pure plutonium, and the lack of a specific US infrastructure Fast reactors can effectively destroy all transuranics Proliferation issue Waste issue GNEP-TD will focus research on fast reactor recycling 12
13 Major Remaining Challenges for Fast Reactors Cost reduction Future deployment Demonstration of passive safety R&D and demonstration program TRU fuels The major issue for transmutation Associated separations processes Coupled decision Metal/pyro or another combination 13
14 SUMMARY GNEP is a redefinition of this country s nuclear energy strategy Set the agenda for years ahead GNEP-TD is the domestic demonstration program to support GNEP goals FY06 is the stand-up phase for GNEP and GNEP-TD Technology development geared to Summer 08 Secretarial decision Discussions have taken place with a number of countries on cooperation 14
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