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Published January 1967 | Version v1
Journal article

Sodium-cooled 1,000 MWe fast breeder reactor design study (1st cycle)

Creators

  • 1. Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)

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

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

Optional Information

Notes
7 refs., 13 figs., 3 tabs.