RAMONA-3B application to Browns Ferry ATWS
The Anticipated Transient Without Scram (ATWS) is known to be a dominant accident sequence for possible core melt in a Boiling Water Reactor (BWR). A recent Probabilistic Risk Assessment (PRA) analysis for the Browns Ferry nuclear power plant indicates that ATWS is the second most dominant transient for core melt in BWR/4 with Mark I containment. The most dominant sequence being the failure of long term decay heat removal function of the Residual Heat Removal (RHR) system. Of all the various ATWS scenarios, the Main Steam Isolation Valve (MSIV) closure ATWS sequence was chosen for present analysis because of its relatively high frequency of occurrence and its challenge to the residual heat removal system and containment integrity. The objective of this paper is to discuss four MSIV closure ATWS calculations using the RAMONA-3B code. The paper is a summary of a report being prepared for the USNRC Severe Accident Sequence Analysis (SASA) program which should be referred to for details. 10 refs., 20 figs., 3 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6476532
- Report Number(s):
- BNL-NUREG-37324; CONF-8510173-43; ON: TI86004357
- Country of Publication:
- United States
- Language:
- English
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RAMONA-3B calculations for Browns Ferry ATWS (Anticipated Transient Without Scram) study
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Related Subjects
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Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONTROL EQUIPMENT
EQUIPMENT
FLOW REGULATORS
MELTDOWN
REACTOR ACCIDENTS
REACTORS
RISK ASSESSMENT
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS