The utilization of research reactors and related facilities for the supporting of innovative power reactor and related fuel cycle
Creators
- 1. Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki-ken 311-1393 (Japan)
Description
Over 30% of electricity in Japan was produced by the existing power reactor 'LWR'. Nuclear power has an advantage to reduce the emission of greenhouse gas 'CO2'. In near future, the LWR are utilized to produce the electricity and it is planned to extend the lifetime to go up the economic efficiency and availability. To meet this technical request, the experimental resolution for the ageing degradation of materials under neutron environment and upgrading the fuel performance are so important issues. rom the viewpoint of energy resource and the reduction of environmental burdens, the innovative nuclear reactor systems are investigated in the worldwide, such as generation IV systems and INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles). In Japan, the demonstration fast breeder reactor is expected to start the operation around 2025. As a key for the realization of the fast breeder reactor system, it is important to improve the fuel performance and to develop the new materials. For this purpose, it is necessary to investigate the fuel behavior to make clear the fuel stability limit and safety margins. The role of research reactor is to figure out the degradation of materials and fuel performance, include the development of new reactor materials. The important thing for the research of fuel performance using the research reactor should be collocated with the fuel fabrication facility for the irradiation test, post-irradiation examination facility, and so on. n Oarai Research and Development Center, there are some research reactors and post-irradiation examination facilities to investigate the fuels and materials for innovative power reactor, such as Fast Reactor, High Temperature Reactor. That is, the research reactors as the thermal neutron irradiation field are Japan Material Test Reactor (JMTR) and High Temperature Test Reactor (HTTR). The Japan Experimental Fast Reactor 'JOYO' is utilized as the fast neutron irradiation field. The JMTR has been used as the irradiation facility for the research the fuels and materials of the existing power reactor and the fundamental research of materials. The JOYO has been used for the research and development of the fuels and materials of the fast breeder reactor and the fundamental research of new materials development for the fusion reactor. The many type of irradiation devices to meet the objectives of irradiation experiments are provided include the instrumented vehicle for JMTR and JOYO. n addition, there are four post-irradiation examination (PIE) facilities and a fuel specimen fabrication facility in Oarai Research and Development Center. Three PIE facilities are to treat the Plutonium fuels. And also it is possible to fabricate the fuel pellets remotely. Furthermore, the reassembling of irradiation vehicles in the hot cell to reload into the reactor is possible. From the view point of the sophisticated irradiation technology, how to contribute in the field of irradiation effects of reactor materials for fission and fusion reactor is under discussion. Thus, it is possible not only to fabricate the fuel specimens, examine the fuels and materials after irradiation, but also to treat and storage the radioactive waste. Besides, the research center of universities for the irradiation behavior of materials is located in the same site. Hence, Oarai Research and Development Center is able to support the research of irradiation behavior for reactor materials and upgrading the reactor fuels, effectively and efficiently
Additional details
Publishing Information
- Imprint Title
- International conference on research reactors: Safe management and effective utilization. Book of extended synopses
- Imprint Pagination
- 297 p.
- Journal Page Range
- p. 32-33
- Report number
- IAEA-CN--156
Conference
- Title
- Safe management and effective utilization
- Acronym
- International conference on research reactors
- Dates
- 5-9 Nov 2007
- Place
- Sydney (Australia)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39043147
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON DIOXIDE; FAST NEUTRONS; FUEL CYCLE; HOT CELLS; HTTR REACTOR; IRRADIATION; JAPAN; JOYO REACTOR; NUCLEAR FUELS; PERFORMANCE; PLUTONIUM; POST-IRRADIATION EXAMINATION; RADIOACTIVE WASTES; RESEARCH REACTORS; TEST REACTORS; THERMAL NEUTRONS; THERMONUCLEAR REACTORS
- Descriptors DEC
- ACTINIDES; ASIA; BARYONS; BREEDER REACTORS; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; DEVELOPED COUNTRIES; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HADRONS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; LABORATORY EQUIPMENT; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; NEUTRONS; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES; TRANSURANIUM ELEMENTS; WASTES
Optional Information
- Secondary number(s)
- IAEA-CN--156/U-35