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Title: Environmentally assisted cracking in light water reactors - annual report, January-December 2001.

Abstract

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from January to December 2001. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of austenitic stainless steels (SSs), (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic SSs, and (c) EAC of Alloy 600. The effects of key material and loading variables, such as strain amplitude, strain rate, temperature, dissolved oxygen (DO) level in water, and material heat treatment, on the fatigue lives of wrought and cast austenitic SSs in air and LWR environments have been evaluated. The mechanism of fatigue crack initiation in austenitic SSs in LWR environments has also been examined. The results indicate that the presence of a surface oxide film or difference in the characteristics of the oxide film has no effect on fatigue crack initiation in austenitic SSs in LWR environments. Slow-strain-rate tensile tests and post-test fractographic analyses were conducted on several model SS alloys irradiated to {approx}2 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) ({approx}3 dpa) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloyingmore » and impurity elements on the susceptibility of these steels to IASCC. Corrosion fatigue tests were conducted on nonirradiated austenitic SSs in high-purity water at 289 C to establish the test procedure and conditions that will be used for the tests on irradiated materials. A comprehensive irradiation experiment was initiated to obtain many tensile and disk specimens irradiated under simulated pressurized water reactor conditions at {approx}325 C to 5, 10, 20, and 40 dpa. Crack growth tests were completed on 30% cold-worked Alloy 600 in high-purity water under various environmental and loading conditions. The results are compared with data obtained earlier on several heats of Alloy 600 tested in high-DO water under several heat treatment conditions.« less

Authors:
; ; ; ; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USNRC
OSTI Identifier:
925064
Report Number(s):
ANL-02/33
TRN: US0803033
DOE Contract Number:  
DE-AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
ENGLISH
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ALLOYS; CORROSION FATIGUE; CRACK PROPAGATION; DISSOLVED GASES; ENVIRONMENTAL EFFECTS; HEAT TREATMENTS; IRRADIATION; OXIDES; OXYGEN; PWR TYPE REACTORS; STAINLESS STEELS; STEELS; STRAIN RATE; STRAINS; STRESS CORROSION

Citation Formats

Chopra, O K, Chung, H M, Clark, R W, Gruber, E E, Hiller, R W, Shack, W J, Soppet, W K, Strain, R V, and Energy Technology. Environmentally assisted cracking in light water reactors - annual report, January-December 2001.. United States: N. p., 2003. Web. doi:10.2172/925064.
Chopra, O K, Chung, H M, Clark, R W, Gruber, E E, Hiller, R W, Shack, W J, Soppet, W K, Strain, R V, & Energy Technology. Environmentally assisted cracking in light water reactors - annual report, January-December 2001.. United States. doi:10.2172/925064.
Chopra, O K, Chung, H M, Clark, R W, Gruber, E E, Hiller, R W, Shack, W J, Soppet, W K, Strain, R V, and Energy Technology. Sun . "Environmentally assisted cracking in light water reactors - annual report, January-December 2001.". United States. doi:10.2172/925064. https://www.osti.gov/servlets/purl/925064.
@article{osti_925064,
title = {Environmentally assisted cracking in light water reactors - annual report, January-December 2001.},
author = {Chopra, O K and Chung, H M and Clark, R W and Gruber, E E and Hiller, R W and Shack, W J and Soppet, W K and Strain, R V and Energy Technology},
abstractNote = {This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from January to December 2001. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of austenitic stainless steels (SSs), (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic SSs, and (c) EAC of Alloy 600. The effects of key material and loading variables, such as strain amplitude, strain rate, temperature, dissolved oxygen (DO) level in water, and material heat treatment, on the fatigue lives of wrought and cast austenitic SSs in air and LWR environments have been evaluated. The mechanism of fatigue crack initiation in austenitic SSs in LWR environments has also been examined. The results indicate that the presence of a surface oxide film or difference in the characteristics of the oxide film has no effect on fatigue crack initiation in austenitic SSs in LWR environments. Slow-strain-rate tensile tests and post-test fractographic analyses were conducted on several model SS alloys irradiated to {approx}2 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) ({approx}3 dpa) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloying and impurity elements on the susceptibility of these steels to IASCC. Corrosion fatigue tests were conducted on nonirradiated austenitic SSs in high-purity water at 289 C to establish the test procedure and conditions that will be used for the tests on irradiated materials. A comprehensive irradiation experiment was initiated to obtain many tensile and disk specimens irradiated under simulated pressurized water reactor conditions at {approx}325 C to 5, 10, 20, and 40 dpa. Crack growth tests were completed on 30% cold-worked Alloy 600 in high-purity water under various environmental and loading conditions. The results are compared with data obtained earlier on several heats of Alloy 600 tested in high-DO water under several heat treatment conditions.},
doi = {10.2172/925064},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2003},
month = {6}
}

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