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

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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 Mary Drouin. 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., & Mary Drouin. 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 Mary Drouin. Sun . "Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results". United States. doi:. 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 Mary Drouin},
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:
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