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.
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收藏
页码：2217 / 2222
页数：6
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