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Title: Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue

Abstract

We present statistical analyses of pressurized water reactor (PWR) primary coolant leak events caused by thermal fatigue, and discuss their safety significance. Our worldwide data contain 13 leak events (through-wall cracking) in 3509 reactor-years, all in stainless steel piping with diameter less than 25 cm. Several types of data analysis show that the frequency of leak events (events per reactor-year) is increasing with plant age, and the increase is statistically significant. When an exponential trend model is assumed, the leak frequency is estimated to double every 8 years of reactor age, although this result should not be extrapolated to plants much older than 25 years. Difficulties in arresting this increase include lack of quantitative understanding of the phenomena causing thermal fatigue, lack of understanding of crack growth, and difficulty in detecting existing cracks.

Authors:
; ;
Publication Date:
Research Org.:
Idaho National Engineering and Environmental Lab., Idaho Falls, ID (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
10169
Report Number(s):
INEEL/CON-99-00320
TRN: US0103368
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Conference
Resource Relation:
Conference: ESREL '99 - European Safety and Reliability Conference, Munich (DE), 09/13/1999--09/17/1999; Other Information: PBD: 1 Sep 1999
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 36 MATERIALS SCIENCE; FAILURE MODE ANALYSIS; PRIMARY COOLANT CIRCUITS; CRACK PROPAGATION; DATA ANALYSIS; PWR TYPE REACTORS; RELIABILITY; REACTOR SAFETY; STAINLESS STEELS; THERMAL FATIGUE; LEAK EVENTS; PRIMARY COOLANT SYSTEM; THROUGH-WALL CRACKING; PRESSURIZED WATER REACTOR

Citation Formats

C. L. Atwood, V. N. Shah, and W. J. Galyean. Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue. United States: N. p., 1999. Web.
C. L. Atwood, V. N. Shah, & W. J. Galyean. Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue. United States.
C. L. Atwood, V. N. Shah, and W. J. Galyean. Wed . "Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue". United States. https://www.osti.gov/servlets/purl/10169.
@article{osti_10169,
title = {Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue},
author = {C. L. Atwood and V. N. Shah and W. J. Galyean},
abstractNote = {We present statistical analyses of pressurized water reactor (PWR) primary coolant leak events caused by thermal fatigue, and discuss their safety significance. Our worldwide data contain 13 leak events (through-wall cracking) in 3509 reactor-years, all in stainless steel piping with diameter less than 25 cm. Several types of data analysis show that the frequency of leak events (events per reactor-year) is increasing with plant age, and the increase is statistically significant. When an exponential trend model is assumed, the leak frequency is estimated to double every 8 years of reactor age, although this result should not be extrapolated to plants much older than 25 years. Difficulties in arresting this increase include lack of quantitative understanding of the phenomena causing thermal fatigue, lack of understanding of crack growth, and difficulty in detecting existing cracks.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {9}
}

Conference:
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