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Title: Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results

Abstract

This paper discusses the core damage frequency (CDF) insights gained by analyzing the results of the Individual Plant Examinations (IPES) for two groups of plants: boiling water reactor (BWR) 3/4 plants with Reactor Core Isolation Cooling systems, and Westinghouse 4-loop plants. Wide variability was observed for the plant CDFs and for the CDFs of the contributing accident classes. On average, transients-with loss of injection, station blackout sequences, and transients with loss of decay heat removal are important contributors for the BWR 3/4 plants, while transients, station blackout sequences, and loss-of-coolant accidents are important for the Westinghouse 4-loop plants. The key factors that contribute to the variability in the results are discussed. The results are often driven by plant-specific design and operational characteristics, but differences in modeling approaches are also important for some accident classes.

Authors:
;  [1];  [2];  [3]
  1. Sandia National Labs., Albuquerque, NM (United States)
  2. Science Applications International Corp., (United States)
  3. Nuclear Regulatory Commission, Washington, DC (United States)
Publication Date:
Research Org.:
Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States); Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
205567
Report Number(s):
SAND-95-3028C; CONF-9510156-9
ON: DE96004182; TRN: 96:008534
DOE Contract Number:  
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: 23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995; Other Information: PBD: [1995]
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR ACCIDENTS; PWR TYPE REACTORS; REACTOR CORES; DAMAGE; OUTAGES; LOSS OF COOLANT; AFTER-HEAT REMOVAL; HEAT TRANSFER; HYDRAULICS; REACTOR SAFETY; TRANSIENTS

Citation Formats

Dingman, S, Camp, S, LaChance, J, and Drouin, Mary. Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results. United States: N. p., 1995. Web.
Dingman, S, Camp, S, LaChance, J, & Drouin, Mary. Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results. United States.
Dingman, S, Camp, S, LaChance, J, and Drouin, Mary. Sun . "Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results". United States. https://www.osti.gov/servlets/purl/205567.
@article{osti_205567,
title = {Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results},
author = {Dingman, S and Camp, S and LaChance, J and Drouin, Mary},
abstractNote = {This paper discusses the core damage frequency (CDF) insights gained by analyzing the results of the Individual Plant Examinations (IPES) for two groups of plants: boiling water reactor (BWR) 3/4 plants with Reactor Core Isolation Cooling systems, and Westinghouse 4-loop plants. Wide variability was observed for the plant CDFs and for the CDFs of the contributing accident classes. On average, transients-with loss of injection, station blackout sequences, and transients with loss of decay heat removal are important contributors for the BWR 3/4 plants, while transients, station blackout sequences, and loss-of-coolant accidents are important for the Westinghouse 4-loop plants. The key factors that contribute to the variability in the results are discussed. The results are often driven by plant-specific design and operational characteristics, but differences in modeling approaches are also important for some accident classes.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {12}
}

Conference:
Other availability
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