Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 2001.05a
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- Pages.266-266
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- 2001
The Features of Probabilistic Safety Assessment in Standard Design of Korean Next Generation Reactor
- Na, Jang-Hwan (Korea Electric Power Research Institute, KEPCO) ;
- Lee, Jae-Sung (Korea Electric Power Research Institute, KEPCO) ;
- Kim, Moon-Chul (Korea Electric Power Research Institute, KEPCO)
- Published : 2001.05.01
Abstract
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