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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 Laboratory (INL)
Sponsoring Org.:
USDOE
OSTI Identifier:
911371
Report Number(s):
INEEL/CON-99-00320
TRN: US0704541
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Conference: ESREL '99 - European Safety and Reliability Conference,Munich, Germany,09/13/1999,09/17/1999
Country of Publication:
United States
Language:
English
Subject:
42 - ENGINEERING, 99 - GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; COOLANTS; CRACK PROPAGATION; DATA ANALYSIS; PWR TYPE REACTORS; RELIABILITY; SAFETY; STAINLESS STEELS; THERMAL FATIGUE; data analysis; leak events; pressurized water reactor (PWR); thermal fatigue

Citation Formats

Atwood, Corwin Lee, Shah, Vikram Naginbhai, and Galyean, William Jospeh. Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue. United States: N. p., 1999. Web.
Atwood, Corwin Lee, Shah, Vikram Naginbhai, & Galyean, William Jospeh. Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue. United States.
Atwood, Corwin Lee, Shah, Vikram Naginbhai, and Galyean, William Jospeh. Wed . "Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue". United States. https://www.osti.gov/servlets/purl/911371.
@article{osti_911371,
title = {Analysis of Pressurized Water Reactor Primary Coolant Leak Events Caused by Thermal Fatigue},
author = {Atwood, Corwin Lee and Shah, Vikram Naginbhai and Galyean, William Jospeh},
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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