日本原子力学会 年会・大会予稿集
2012 Annual Meeting
セッションID: C38
会議情報
ペブルベット型原子炉
DESIGN STUDY OF INNOVATIVE SIMPLIFIED SMALL PEBBLE BED REACTOR
(5) PASSIVE SAFETY ANALYSIS FOR DECAY HEAT REMOVAL WITHOUT FORCED COOLING
*DWI IRWANTOTORU OBARA
著者情報
会議録・要旨集 フリー

詳細
抄録
Neutronic and burnup analysis have been performed in the previous study for a small simplified pebble bed reactor using both uranium and thorium fuel. In the present study, decay heat removal without forced cooling in the accident condition of a simplified pebble bed reactor with peu a peu fuel loading scheme are going to be performed.
著者関連情報
© 2012 Atomic Energy Society of Japan
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