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大型高速炉設計研究成果報告書; 60万KWe級プラントの設計研究

Progress report of the design study on a large scale reactor; Design study on a 600MWe class plant

林 秀行; 永田 敬; 森山 正敏; 石川 真; 中大路 道彦; 黒木 修二; 山岡 光明

Hayashi, Hideyuki; not registered; not registered; not registered; not registered; not registered; Yamaoka, Mitsuaki

大洗工学センターのプラント工学室では、平成2年度から、実用高速炉としてほぼ下限の出力規模と想定される60万kWe級プラントを対象として、電気事業者の行う実証炉の設計研究を適切に支援出来る技術的基盤を確立する事を主要目的とする「大型炉設計研究」を、大洗工学センター関連部課室の参画・協力を得て全所的展開の中で実施してきた。本プラントの特長はループ型炉の本質的な長所を活かした1次主冷却系配管の短縮技術、系統の簡素化・信頼性向上、格納容器床下のメンテナンスフリー化等の基本的コンセプトを統合した「原子炉容器ヘッドアクセス方式」にあり、遮蔽プラグや燃料取扱系統の抜本的簡素化、プルトニウムの需給バランスに柔軟に対応出来る炉心概念等、原型炉までの技術・経験を活かしつつ高速炉の実用化に必要な技術的ブレークスルーにも挑戦したプラント概念になっている。本報告は、電気事業者の建設意欲を喚起出来る実証炉段階のプラント概念を提示したこれら設計研究の成果を原子炉設置許可申請書の本文相当の「系統設計」、添付書類8相当の「各部設計」、添付書類10相当の「安全設計方針及び安全評価」、及び関連する「研究開発課題」に区分して整理・記述したものである。

A design study on a large scale fast reactor was performed at OEC about 600 MWe class plant which might be the lowest power scale as a commercial one. The purpose of the study is set to present a plant concept which could stand together reality at the demonstration stage and innovativeness through commercialization, as well as to establish technological basis to support the design study of the utilities' plant. Features of this plant are as follows. (1)Application of intrinsic merit of a loop type plant, and introduction of a reactor-vessel-head-access-piping system which produces a new concept of primary piping shortening technology, simplification of cooling systems, improvement in reliability of components, and free-maintenance of equipments underneath the operating floor. (2)Plant design based on the technologies and experiences up to the prototype reactor, and also challenge to the technological breakthrough for the commercialization of FBR, such as drastic simplification of a shielding plug and a spent fuel handling system. This report describes the result of a design study on a large scale FBR plant, which will motivate utilities to construct the demonstration plant. This report eonsists of three parts of "System Design," "Sub-system Designs" and "Safety Design Guide and Safety Evaluation" which correspond to the text, the appendix VIII and the appendix X of the application of reactor construction permit respectively, and a part of R&D subjects derived from the design study.

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