Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan
2012 Annual Meeting
Session ID : C38
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DESIGN STUDY OF INNOVATIVE SIMPLIFIED SMALL PEBBLE BED REACTOR
(5) PASSIVE SAFETY ANALYSIS FOR DECAY HEAT REMOVAL WITHOUT FORCED COOLING
*DWI IRWANTOTORU OBARA
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Abstract
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.
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© 2012 Atomic Energy Society of Japan
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