Design summary of top entry type FBR demonstration reactor
Creators
- 1. Japan Atomic Power Co., Tokyo (Japan)
Description
As for the demonstration reactor following the prototype FBR 'Monju', Japan Atomic Power Co. has advanced the research on the design with the cooperation of the organizations concerned, and the technical development is in progress. In fiscal years 1990 and 1991, the outline design of the main systems, machinery and equipment of the top entry, loop type demonstration reactor and the technical evaluations of structural integrity, safety, operation, maintenance and others have been carried out, and its technical feasibility was confirmed. In this report, the features, the concept of the structure and the results of the technical evaluation of the top entry, loop type FBR are outlined. The course of FBR development so far is summarized. The designs of the whole plant, the core and fuel, the structure of the reactor, the machinery and equipment of the cooling system, safety and protection facilities and fuel handling system, and the technical evaluation of safety, structural integrity, confirmation test, operation and maintenance and economy are reported. (K.I.)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.35.268Abstract (Japanese)
高速増殖原型炉「もんじゅ」に続く実証炉については、日本原子力発電(株)が関係機関の協力を得て設計研究を進め、各機関が協力して技術開発を進めている。1990,1991年度には、トップエントリー方式ループ型実証炉の主要系統·機器の概略設計と構造健全性、安全性、運転·保守性等に関する技術評価を行い技術的に成立することを確認している。本稿では、トップエントリー方式ループ型炉の特徴と構造概念および技術評価結果について解説する。 (日本)Additional details
Additional titles
- Original title (Japanese)
- トップエントリー型FBR実証炉の概要
Identifiers
- DOI
- 10.3327/jaesj.35.268;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 35
- Journal Issue
- 4
- Journal Page Range
- p. 268-279
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54063497
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUEL ELEMENTS; LMFBR TYPE REACTORS; MECHANICAL STRUCTURES; REACTOR CHARGING MACHINES; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR VESSELS; RELIABILITY
- Descriptors DEC
- BREEDER REACTORS; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MAINTENANCE; OPERATION; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR OPERATION; REACTORS; SAFETY
Optional Information
- Notes
- This record replaces 24070180