動力・エネルギー技術の最前線講演論文集 : シンポジウム
Online ISSN : 2424-2950
セッションID: F213
会議情報
F213 実用化に向けたナトリウム冷却高速炉原子炉構造の信頼性向上に関する検討(FBR(2),OS-8 軽水炉・新型炉・核燃料サイクル(3),一般講演,地球温暖化防止と動力エネルギー技術)
阪本 善彦久保 重信小竹 庄司神島 吉郎
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会議録・要旨集 フリー

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This paper describes the enhancement of reliability for components of the reactor system in JSFR (JAEA Sodium-cooled Fast Reactor) design. As for manufacturability, compact design of the Reactor Vessel (RV) enables its manufacture in a factory. This results in high quality welding and in precise machining of the RV. The adoption of ring-shaped forgings contributes for securing the reliability against thermal stress as well as securing the dimension precision. Regarding maintenability, the in-vessel structures have simple configurations, so it is comparatively easy for inspection equipments to reach inspection targets. In the JSFR design, sodium boundary area is reduced significantly, which makes double-walled design of the piping easier, and reduces welding lines. So, the reactor system of JSFR is desirable to inspect the in-vessel structures efficiently, and there is a prospect of reliable plant operation. Advanced inspection technologies are also under development for the inspection of the in-vessel structures under sodium.
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© 2008 一般社団法人 日本機械学会
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