Sodium-cooled 1,000 MWe fast breeder reactor design study (1st cycle)
Description
This is a brief summary of a design study undertaken in the Japan Atomic Energy Research Institute on a 1,000 MWe sodium-cooled fast reactor. The following conditions were adopted as the design targets: Good breeding ratio in the reactor core; small positive reactivity of sodium void in the central channel of the core; 2-zoned power flattening by optimizing the core material composition, reasonable maximum clad temperature for cladding. PuO2-UO2 mixed oxide was chosen as fuel material. A rotating core concept was considered for refueling. A total breeding ratio of 1.44 was obtained. A doubling time of about 9 years is possible with this design. A rough estimate of power cost gives a value of 1.48 yen/kWh. (author)
Additional details
Additional titles
- Original title (Japanese)
- Na冷却100万kW高速増殖炉プラント概念設計(第1次)
Identifiers
- DOI
- 10.3327/jaesj.9.16;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 9
- Journal Issue
- 1
- Series
- 雑誌名:日本原子力学会誌
- Journal Page Range
- p. 16-24
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 55022923
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BREEDING RATIO; BURNUP; FUEL ASSEMBLIES; HEAT FLUX; MIXED OXIDE FUELS; NEUTRON FLUX; REACTIVITY; REACTOR DESIGN; SODIUM COOLED REACTORS; TBR TOKAMAK; VOID COEFFICIENT
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONVERSION RATIO; DESIGN; DIMENSIONLESS NUMBERS; ENERGY SOURCES; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; NUCLEAR FUELS; RADIATION FLUX; REACTIVITY COEFFICIENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Notes
- 7 refs., 13 figs., 3 tabs.