Study of core characteristics on fuel and coolant type. Results in FY1999
Creators
- 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
Feasibility studies (F/S) have been undertaken since July, 1999 in order to determine promising concepts of a commercialized fast reactor cycle system and to define the related necessary R and D tasks. In the phase I(FYs of 1999-2000) of this F/S, a number of conceptual candidates are selected from the following 5 viewpoints: a) ensuring safety, b) economic competitiveness to future LWRs, c) efficient utilization of resources, d) reduction of environmental burden, e) enhancement of nuclear non-proliferation. As for this study based on the above viewpoints, core characteristics of many kinds of reactors have been surveyed and classified in the combinations of fuel (MOX, metal and nitride) and coolant (sodium, lead, lead-bismuth, carbon dioxide and helium) types and power output scales. As a result, R and D items to be performed have been proposed, and a data base to select candidate reactor concepts has been constructed. The intermediate results obtained in the first FY of the phase I are as follows: (1) There are many years of experience for the MOX fuel compared with metal and nitride fuels. However, metal and nitride fuels are excellent for breeding and doubling time. (2) The metal fuel has the cladding temperature limit corresponding to the core outlet temperature of 510-530degC, due to the fuel-clad compatibility problem which is lower than in the MOX fuel case. A new cladding material should be developed to achieve the higher temperature. (3) The nitride fuel has the demerits due to estrangement of nitrogen under accident conditions and also due to the necessity of enrichment of 15N. (4) Some high burnup experience has been accumulated for the metal fuel and even less for the nitride fuel. Experiential evaluation of high-burnup behaviors and accumulation of high-burnup fuel irradiation experiences are indispensable for making these fuels a general high-burnup fuel concept. (5) From the core characteristics, there is no difference among sodium, heavy-metal and gas coolants. (author)
Availability note (English)
Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781 (domestic), FAX: +81-3-3979-2210 (oversea)Additional details
Publishing Information
- Imprint Pagination
- 452 p.
- Report number
- JNC-TY--9400-2000-021
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 33012797
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COOLANTS; DEMONSTRATION PROGRAMS; DESIGN; FBR TYPE REACTORS; FEASIBILITY STUDIES; FUEL CANS; GASES; LEAD; METALS; MIXED OXIDE FUELS; REACTOR CORES; SODIUM; URANIUM NITRIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALKALI METALS; BREEDER REACTORS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FLUIDS; FUELS; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; PNICTIDES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; URANIUM COMPOUNDS
Optional Information
- Notes
- 35 refs., 158 figs., 117 tabs.