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Title: Synergistic failure of BWR internals

Abstract

Boiling Water Reactor (BWR) core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. An initial phase has been completed in which background material was gathered and evaluated, and potential accident sequences were identified. A second phase is underway to perform a simplified, quantitative probabilistic risk assessment on a representative high-power BWR/4. Results of the initial study conducted on the jet pumps show that any cascading failures would not result in a significant increase in the core damage frequency. The methodology is currently being extended to other major reactor internals components.

Authors:
 [1];  [2]
  1. (INEEL)
  2. (NRC)
Publication Date:
Research Org.:
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
758130
Report Number(s):
INEEL/CON-99-01142
TRN: US0003762
DOE Contract Number:  
AC07-99ID13727
Resource Type:
Conference
Resource Relation:
Conference: Water Reactor Safety Meeting, Bethesda, MD (US), 10/25/1999--10/27/1999; Other Information: PBD: 25 Oct 1999
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; SHROUDS; REACTOR COMPONENTS; REACTOR ACCIDENTS; RISK ASSESSMENT; STRESS CORROSION; INTERGRANULAR CORROSION; CRACK PROPAGATION; FAILURES; BOILING WATER REACTOR; CORE SHROUDS; INTERGRANULAR STRESS CORROSION CRACKING (IGSCC); VESSEL INTERNALS; ACCIDENT SEQUENCES; CASCADING FAILURES

Citation Formats

A. G. Ware, and T. Y. Chang. Synergistic failure of BWR internals. United States: N. p., 1999. Web.
A. G. Ware, & T. Y. Chang. Synergistic failure of BWR internals. United States.
A. G. Ware, and T. Y. Chang. Mon . "Synergistic failure of BWR internals". United States. doi:. https://www.osti.gov/servlets/purl/758130.
@article{osti_758130,
title = {Synergistic failure of BWR internals},
author = {A. G. Ware and T. Y. Chang},
abstractNote = {Boiling Water Reactor (BWR) core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. An initial phase has been completed in which background material was gathered and evaluated, and potential accident sequences were identified. A second phase is underway to perform a simplified, quantitative probabilistic risk assessment on a representative high-power BWR/4. Results of the initial study conducted on the jet pumps show that any cascading failures would not result in a significant increase in the core damage frequency. The methodology is currently being extended to other major reactor internals components.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Oct 25 00:00:00 EDT 1999},
month = {Mon Oct 25 00:00:00 EDT 1999}
}

Conference:
Other availability
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