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Title: Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1

Technical Report ·
DOI:https://doi.org/10.2172/6370654· OSTI ID:6370654

An analysis of five anticipated transients without scram (ATWS) was conducted at the Idaho National Engineering Laboratory (INEL). The five detailed deterministic simulations of postulated ATWS sequences were initiated from a main steamline isolation valve (MSIV) closure. The subject of the analysis was the Browns Ferry Nuclear Plant Unit 1, a boiling water reactor (BWR) of the BWR/4 product line with a Mark I containment. The simulations yielded insights to the possible consequences resulting from a MSIV closure ATWS. An evaluation of the effects of plant safety systems and operator actions on accident progression and mitigation is presented.

Research Organization:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6370654
Report Number(s):
NUREG/CR-4165; EGG-2379; ON: TI87010676
Country of Publication:
United States
Language:
English