Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1997.10a
- /
- Pages.713-718
- /
- 1997
Advanced In-Vessel Retention Design for Next Generation Risk Management
- Kune Y. Suh (Seoul National University Department of Nuclear Engineering) ;
- Hwang, Il-Soon (Seoul National University Department of Nuclear Engineering)
- Published : 1997.10.01
Abstract
In the TMI-2 accident, approximately twenty(20) tons of molten core material drained into the lower plenum. Early advanced light water reactor (LWR) designs assumed a lower head failure and incorporated various measures for ex-vessel accident mitigation. However, one of the major findings from the TMI-2 Vessel Investigation Project was that one part of the reactor lower head wall estimated to have attained a temperature of 1100
Keywords