Treatment of phenomenological uncertainties in a LWR severe accident risk analysis computer code

被引：0

作者：

Sehgal, BR ^{[1
]}

Bui, VA ^{[1
]}

Dinh, TN ^{[1
]}

Nourgaliev, RR ^{[1
]}

机构：

[1] Royal Inst Technol, Div Nucl Power Safety, S-10044 Stockholm, Sweden

来源：

PROBABILISTIC SAFETY ASSESSMENT AND MANAGEMENT (PSAM 4), VOLS 1-4 | 1998年

关键词：

D O I：

暂无

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

This paper presents the modeling method employed in, and application of, a computer code named SAPHIRA (Severe Accident Phenomenological and integrated Risk Analyzer). This code is intended as a vehicle for analyzing both in-vessel and ex-vessel core melt progression in a Swedish boiling water reactor (BWR) plant.

引用

页码：2217 / 2222

页数：6

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