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Draft of standard for graphite core components in High Temperature Gas-cooled Reactor

高温ガス炉黒鉛構造物規格原案

柴田 大受 ; 衛藤 基邦*; 國本 英治*; 塩沢 周策; 沢 和弘; 奥 達雄*; 丸山 忠司*

Shibata, Taiju; Eto, Motokuni*; Kunimoto, Eiji*; Shiozawa, Shusaku; Sawa, Kazuhiro; Oku, Tatsuo*; Maruyama, Tadashi*

高温工学試験研究炉(HTTR)の黒鉛構造物の設計にあたっては日本原子力研究開発機構で独自に定めた黒鉛構造設計方針等が適用されたが、実用高温ガス炉のための標準化した規格体系は整備されていない。そこで著者らは、黒鉛構造物の規格化のために必要な技術的課題を検討し、資料として取りまとめた。その内容は日本原子力学会「高温ガス炉黒鉛構造物規格化のための調査検討」特別専門委員会において議論され、高温ガス炉黒鉛構造物規格原案として取りまとめられた。本規格原案は、黒鉛構造物の安全機能と交換性の観点から、黒鉛構造物を3種類のクラス(クラスA, B及びC)とし、それぞれのクラスの構造物について、設計規格,材料・製品規格,供用期間中検査・維持基準について定めた世界で初めて高温ガス炉黒鉛構造物の規格の考え方を提示したものである。

For the design of the graphite components in the High Temperature Engineering Test Reactor (HTTR), the graphite structural design code for the HTTR etc. were applied. However, general standard systems for the High Temperature Gas-cooled Reactor (HTGR) have not been established yet. The authors had studied on the technical issues which is necessary for the establishment of a general standard system for the graphite components in the HTGR. The results of the study were documented and discussed at a "Special committee on research on preparation for codes for graphite components in HTGR" at Atomic Energy Society of Japan (AESJ). As a result, "Draft of Standard for Graphite Core Components in High Temperature Gas-cooled Reactor" was established. In this draft standard, the graphite components are classified three categories (A, B and C) in the standpoints of safety functions and possibility of replacement. For the components in the each class, design standard, material and product standards, and in-service inspection and maintenance standard are determined. This draft standard is the first standard in the world which shows the concept of standard for the graphite core components in HTGR.

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