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Title: Probabilistic fracture analysis of reactor pressure vessel steels: Joint EPRI-CRIEPI RPV embrittlement studies. Final report

Abstract

This report is presented in two parts to describe the development of analytical procedures to predict the likelihood of the initiation and propagation of cracks in nuclear reactor pressure vessel materials and to compare these predictions with actual data obtained from various sources. Part 1 describes the development of a fracture toughness Master Curve approach that provides a description of fracture probability as a function of normalized temperature (T-RT{sub NDT}). This Master Curve was validated using fracture toughness data for reactor pressure vessel steels and weldments produced in the United States ten to twenty years ago. Additionally, information is provided to show the inadequacies of currently applied models which tend to over predict materials failure and have led to very conservative estimates of limiting (i.e., lower bound) material reference toughness. Part 2 describes the work performed to compare data obtained in a recent Japanese round-robin testing program with predictions obtained by the Master Curve approach. The Japanese steels tend to have higher toughness than the older US steels, but the Master Curve approach accounts for these differences by indexing the temperature relative to RT{sub NDT}.

Authors:
;  [1]
  1. Texas A and M Univ., College Station, TX (United States). Research Foundation
Publication Date:
Research Org.:
Electric Power Research Inst., Palo Alto, CA (United States); Texas A and M Univ., College Station, TX (United States). Research Foundation
Sponsoring Org.:
Electric Power Research Inst., Palo Alto, CA (United States); Central Research Inst. of Electric Power Industry, Tokyo (Japan)
OSTI Identifier:
146795
Report Number(s):
EPRI-TR-105027
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Oct 1995
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 36 MATERIALS SCIENCE; NUCLEAR POWER PLANTS; PRESSURE VESSELS; FRACTURE PROPERTIES; REACTOR MATERIALS; STEELS; CRACKS; CRACK PROPAGATION; JAPAN; USA; COMPARATIVE EVALUATIONS; RADIATION EFFECTS; EMBRITTLEMENT; FRACTURE MECHANICS; EXPERIMENTAL DATA

Citation Formats

Anderson, T L, and Stienstra, D. Probabilistic fracture analysis of reactor pressure vessel steels: Joint EPRI-CRIEPI RPV embrittlement studies. Final report. United States: N. p., 1995. Web.
Anderson, T L, & Stienstra, D. Probabilistic fracture analysis of reactor pressure vessel steels: Joint EPRI-CRIEPI RPV embrittlement studies. Final report. United States.
Anderson, T L, and Stienstra, D. Sun . "Probabilistic fracture analysis of reactor pressure vessel steels: Joint EPRI-CRIEPI RPV embrittlement studies. Final report". United States.
@article{osti_146795,
title = {Probabilistic fracture analysis of reactor pressure vessel steels: Joint EPRI-CRIEPI RPV embrittlement studies. Final report},
author = {Anderson, T L and Stienstra, D},
abstractNote = {This report is presented in two parts to describe the development of analytical procedures to predict the likelihood of the initiation and propagation of cracks in nuclear reactor pressure vessel materials and to compare these predictions with actual data obtained from various sources. Part 1 describes the development of a fracture toughness Master Curve approach that provides a description of fracture probability as a function of normalized temperature (T-RT{sub NDT}). This Master Curve was validated using fracture toughness data for reactor pressure vessel steels and weldments produced in the United States ten to twenty years ago. Additionally, information is provided to show the inadequacies of currently applied models which tend to over predict materials failure and have led to very conservative estimates of limiting (i.e., lower bound) material reference toughness. Part 2 describes the work performed to compare data obtained in a recent Japanese round-robin testing program with predictions obtained by the Master Curve approach. The Japanese steels tend to have higher toughness than the older US steels, but the Master Curve approach accounts for these differences by indexing the temperature relative to RT{sub NDT}.},
doi = {},
url = {https://www.osti.gov/biblio/146795}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {10}
}

Technical Report:
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