期刊
ANNALS OF NUCLEAR ENERGY
卷 196, 期 -, 页码 -出版社
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2023.110196
关键词
PRA; PSA; Safety assessment; Multi-unit PSA (MUPSA); Site risk assessment (SRA); Source term category (STC); Level 3 MUPSA; Level 3 SRA; Site release category (SRC)
By introducing dose-estimates as grouping variables, the site release category (SRC) model allows for manageable analysis of multiple-unit STCs and produces reasonable and conservative results.
Unmanageable numbers of single-unit source term categories (STCs) and multiple-unit STCs (STC combinations) are generally derived from the level 1 & sdot;2 site risk assessment (SRA). Hence it is practically impossible to evaluate the consequence for all STCs in the level 3 SRA process. Also, the representative source terms may cause an optimistic or too conservative results compared to the reference case derived by analyzing the consequences of all STCs in a site. To make the level 3 SRA possible considering these limitations, a site release category (SRC) model based on dose-estimates has been developed only for the multi-unit STCs. By introducing the early and overall dose-estimates as new grouping variables, the SRC model could generate the manageable numbers of SRCs and show the reasonable results with a little conservativeness. As a result of applying the SRC model to the three-unit SRA model, 228 STC combinations are grouped into 22 SRCs and the site risk from the SRC model is about 1% higher than the reference site risk derived by analyzing the consequences of all single and multiple-unit STCs. Hence, from the SRC model, SRA can be performed with the manageable numbers of consequence analyses and the reasonable conservativeness of results.
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