technology transfer to, the private sector will constitute an important element of the reoriented breeder program. A major thrust of the FY 1985 program will be the emphasis on international collaboration in breeder technology to reduce U.S. program costs and to retain the U.S. role in international nuclear forums. The experience gained in design, component testing, licensing, and analysis from the CRBRP Project, as well as our advanced breeder knowledge acquired from `the operation of the Fast Flux Test Facility (FFTF) and the base program, will be valuable in establishing exchange agreements with other nations. A smaller scale effort, the Water-Cooled Breeder Program, is devoted to proving that breeding can be achieved in a light-water reactor using the uranium-233/thorium fuel system. Efforts in FY 1985 will continue the defueling activities and core evaluation of the light-water breeder core from the Shippingport Atomic Power Station. Clinch River Breeder Reactor Project There were no funds appropriated to continue the Clinch River Project in FY 1984. Therefore, on November 10, 1983, the parties involved -- the Department of Energy (DOE), Tennessee Valley Authority (TVA), Commonwealth Edison, Project Managment Corporation (PMC), and the Breeder Reactor Corporation (BRC) agreed to terminate the project, effective November 14, 1983. The agreement was formalized on December 19, 1983. Termination activities began in early FY 1984 and are planned for completion in early FY 1985. These include the termination and/or relocation of project personnel; termination of contracts and subcontracts; site redress work; settlement of terminated contracts and subcontracts; documentation of certain completed work; completion of selected computer verification efforts that were approaching completion when the project was terminated; arrangement for retention and appropriate availability of scientific and technical information generated under the project; storage, maintenance, relocation of CRBRP components, equipment, materials, etc., for use within the LMFBR Program and other Government programs, as appropriate; and disposition of inventories not of value to the LMFBR Program. Large-Scale Prototype Breeder The Government-sponsored design efforts on a Large-Scale Prototype Breeder (LSPB) plant will be phased out in an orderly manner during FY 1984. The program has been a joint effort of the U.S. Government and private industry to develop a large-scale prototypical breeder demonstration plant. The plant was to have been the logical follow-on to the Clinch River Project as a full-scale demonstration plant. The LSPB design will be maintained as a frame of reference for benchmarking advanced concepts developed under the base program. LMFBR Base Program The mission of the LMFBR Base Program is to develop the requisite technology to the point where the private sector is able to construct and operate safe, reliable liquid metal fast breeder reactor plants for supplying electricity to the grid. This includes studies of the technical features applicable to future private sector initiatives. The program has been reoriented to place primary emphasis on designing less complicated safety systems and achieving economic competitiveness in future advanced concepts. It is to this end that the breeder technology and test facilities efforts discussed in the following paragraphs are directed. Concepts and Requirements Development. An effort will be initiated to identify plant concepts that could be developed by industry for use in the marketplace and to assess unique market needs that can be satisfied by the breeder technology program. During FY 1985, development efforts on the advanced concept studies will be conducted by contractors selected during FY 1984 as part of a competitive procurement process. This effort will include development of plant requirements and safety criteria; safety analyses; licensing assessments; seismic evaluation; constructability assessment; identification of research and development requirements; and analysis of cost and schedule potential. Market analysis will be conducted to assure proper program and concept development. The studies will utilize to the maximum extent possible previously developed technology and information gained under current international collaborations, including the DOE-Japanese MONJU agreement. Research and development requirements will be constantly coordinated with other parts of the base program. Beginning in FY 1984 and during FY 1985, an information exchange will be conducted with the Nuclear Regulatory Commission (NRC), aimed at developing licensing criteria for future advanced LMFBRS. Key LMFBR issues will be identified and used as a basis for improving the licensability of LMFBRs and contributing to an efficient licensing process. Power Conversion Technology. It is essential that major cost reduction and reliability potentials are realized in order to justify investor and public acceptance to build and operate economically competitive LMFBRS. The Power Conversion Technology Program focuses on these potentials and encompasses the power conversion systems and the components necessary to convert heat to electricity. Standardized plants and more cost-effective methods for achieving quality assurance are two concepts of special interest for accomplishing the reduced cost and increased reliability goals. The research and development to improve the performance predictability and reliability of power conversion components include flow-induced vibration analysis, flow distribution testing and analysis, mixing and stratification testing and analysis, subcomponent development and testing, fabrication process development, inspection development, and procedure development. Efforts are underway to develop data on materials properties, including fabrication and environmental effects. Documentation of these data in handbook form will serve as an authoritative source for use in the design and licensing processes. The program also includes the development of a new ferritic alloy that offers significant economic and engineering advantages over current reference structural alloys. Significant accomplishments for FY 1984 include: successful completion of sodium testing of the 35,000 gpm pump, which disclosed the need for modifications that would not otherwise have been discovered; successful completion of sodium testing of the hockey stick steam generator in both the recirculation and once-through modes; and successful completion of water testing of the 85,000 gpm two-stage prime pump, preparatory to shipping all pump system parts to ETEC by the end of 1984. Specific accomplishments planned for FY 1985 include: to continue preparations for sodium testing of the helical coil model steam generator; to develop a 14,000 gpm electromagnetic primary sodium pump for modular reactor applications; and to initiate balance-of-plant cost reduction, simplification, and standardization studies. Fabrication of the 70 MWt double-wall tube steam generator will continue, with delivery in FY 1986. Development of this component has the long-term potential for eliminating the intermediate sodium system and avoiding the need for a sodium-water reaction product separation system. Fuel Performance and Supply. The objectives of the Fuel Performance and Supply Program include proving the performance of fuel, blanket, and absorber core components under prototypic operating conditions and demonstrating safe, reliable, and licensable core systems. Specific objectives include extending the lifetime of core components to a minimum of 3 years; automating fuel fabrication to achieve competitive fabrication costs; improving safeguards and reducing personnel exposure; and transferring developed technology to industry. The development of carbide and metal fuels for advanced and smaller sized plants will proceed because of the potential advantages in smaller control requirements, smaller sizes, and lower fuel cycle costs that these fuel systems offer. International participation in the Core Systems and Materials Program will continue to reduce program costs while maximizing technological benefits. In the fuel supply area, activities will continue toward completing the Secure Automated Fabrication (SAF) line. Procurement of equipment and its installation in the Fuels and Materials Engineering Facility (FMEF) will continue. Upon its completion and operation in the late 1980's, the SAF line will demonstrate breeder fuel fabrication technology that can be deployed commercially by industry. Activities for fuel assembly capability in the FMEF will be initiated in FY 1985. Nuclear Systems Technology. The disciplines of safety, physics, structures, thermal hydraulics, and reactor core design are integrated into a single, cohesive unit in the Nuclear Systems Technology Program. The program will focus on experimental verification, in existing DOE facilities, of the feasibility of advanced reactor concepts of varied design, size, and fuel type that exhibit self-terminating capability under failure conditions. All functions needed to assure nuclear safety under abnormal conditions are integrated into the nuclear systems. of inherently safe operation of nuclear systems will reduce the requirements for supporting auxiliary equipment whose purpose Such support Demonstration is to control otherwise dangerous conditions. equipment substantially increases the complexity of reactor designs. These studies will enable the development of a reliable advanced technology that is competitive and compatible with user needs and capabilities. Varied fuel types (metal, oxide, carbide) and fuel pin sizes will be evaluated, as well as the effects of varied core designs on voiding, temperature, and reactivity coefficients. Features supporting inherently safe operation will be developed, reflecting the redirection in the safety program, which places more emphasis |