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Title: BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel

Abstract

To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials.

Authors:
Publication Date:
Research Org.:
Electric Power Research Institute (US)
Sponsoring Org.:
USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
OSTI Identifier:
839513
Report Number(s):
1008189NP
TRN: US200509%%837
DOE Contract Number:  
FC07-03ID14536
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 15 Mar 2005
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; CRACK PROPAGATION; EPRI; FRACTURE PROPERTIES; IRRADIATION; MATRICES; RECOMMENDATIONS; STAINLESS STEELS; TESTING; WATER; BOILING WATER REACTOR; IRRADIATION DAMAGE; STRESS CORROSION CRACKING; FRACTURE TOUGHNESS

Citation Formats

Gilman, J. BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel. United States: N. p., 2005. Web. doi:10.2172/839513.
Gilman, J. BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel. United States. doi:10.2172/839513.
Gilman, J. Tue . "BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel". United States. doi:10.2172/839513. https://www.osti.gov/servlets/purl/839513.
@article{osti_839513,
title = {BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel},
author = {Gilman, J},
abstractNote = {To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials.},
doi = {10.2172/839513},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2005},
month = {3}
}