年次大会講演論文集
Online ISSN : 2433-1325
セッションID: 3510
会議情報
3510 1万kWe超小型高速炉(4S炉)の受動安全特性(S49-1 安全,材料,原子炉用機器,S49 原子炉システムおよびその要素技術)
松宮 壽人坂下 嘉章坪井 靖松本 弘植田 伸幸
著者情報
会議録・要旨集 フリー

詳細
抄録
A conceptual design of sodium cooled fast reactor as small-decentralized power supply has been performed. The reactor named 4S (Super Safe, Small and Simple) has a reflector controlled U-Zr metallic fuel core. Characteristics of the 4S reactor are non-refueling (core life time: 30 years), the negative coolant void reactivity during 30 years, integrated and simple reactor structure, and natural circulation decay heat removal systems. Accidents without scram events (AWS) as unprotected sudden loss of flow event and ATWS events have been analyzed for the passive safety features of 4S using a transient simulation code (ARGO-3 code). It is predicts that the passive safety can evade sever damages of the core and primary coolant boundary under the ATWS and AWS events.
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© 2005 一般社団法人日本機械学会
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