Comparison of probabilistic safety assessment methodologies for nuclear fuel reprocessing and nuclear power plants

被引：0

作者：

Wu, Z.W. ^{[1
]}

Xi, S.R. ^{[1
]}

机构：

[1] Inst. of Nucl. Ener. Tech., Tsinghua Univ., Beijing 100084, China

来源：

Qinghua Daxue Xuebao/Journal of Tsinghua University | 2000年 / 40卷 / 12期

关键词：

Accident prevention - Nuclear materials safeguards - Nuclear power plants - Probability;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

The safe design and the operation of a reactor spent fuel reprocessing plant need a probabilistic safety assessment (PSA). The practical experience, gained from using PSA for domestic nuclear power plants and from studying PSA methods for foreign nuclear fuel reprocessing plants was used in the study. This paper compared the main design safety principles, PSA methodologies, reliability data and accident radiometric consequences, etc. A specific PSA method for nuclear fuel reprocessing plants, that is the stand-alone fault tree deductive technique, is recommended for a safety analysis.

引用

页码：1 / 3

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