skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18

Abstract

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) during the six months from October 1993 to March 1994. EAC and fatigue of piping, pressure vessels, and core components in LWRs are important concerns in operating plants and as extended reactor lifetimes are envisaged. Topics that have been investigated include (a) fatigue of low-alloy steel used in piping, steam generators, and reactor pressure vessels, (b) EAC of wrought and cast austenitic stainless steels (SSs), and (c) radiation-induced segregation and irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS after accumulation of relatively high fluence. Fatigue tests have been conducted on A302-Gr B low-alloy steel to verify whether the current predictions of modest decreases of fatigue life in simulated pressurized water reactor water are valid for high-sulfur heats that show environmentally enhanced fatigue crack growth rates. Additional crack growth data were obtained on fracture-mechanics specimens of austenitic SSs to investigate threshold stress intensity factors for EAC in high-purity oxygenated water at 289{degrees}C. The data were compared with predictions based on crack growth correlations for wrought austenitic SS in oxygenated water developed at ANL and rates in air frommore » Section XI of the ASME Code. Microchemical and microstructural changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating boiling water reactors were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements, which are not specified in the ASTM specifications, may contribute to IASCC of solution-annealed materials.« less

Authors:
; ; ; ; ; ; ; ;  [1]
  1. Argonne National Lab., IL (United States)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Argonne National Lab., IL (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
45615
Report Number(s):
NUREG/CR-4667-Vol.18; ANL-95/2-Vol.18
ON: TI95009017; TRN: 95:010925
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Mar 1995
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; PWR TYPE REACTORS; SAFETY ANALYSIS; BWR TYPE REACTORS; REACTOR COMPONENTS; CORROSION FATIGUE; CRACK PROPAGATION; PROGRESS REPORT; REACTOR SAFETY

Citation Formats

Chung, H M, Chopra, O K, Erck, R A, Kassner, T F, Michaud, W F, Ruther, W E, Sanecki, J E, Shack, W J, and Soppet, W K. Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18. United States: N. p., 1995. Web. doi:10.2172/45615.
Chung, H M, Chopra, O K, Erck, R A, Kassner, T F, Michaud, W F, Ruther, W E, Sanecki, J E, Shack, W J, & Soppet, W K. Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18. United States. doi:10.2172/45615.
Chung, H M, Chopra, O K, Erck, R A, Kassner, T F, Michaud, W F, Ruther, W E, Sanecki, J E, Shack, W J, and Soppet, W K. Wed . "Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18". United States. doi:10.2172/45615. https://www.osti.gov/servlets/purl/45615.
@article{osti_45615,
title = {Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18},
author = {Chung, H M and Chopra, O K and Erck, R A and Kassner, T F and Michaud, W F and Ruther, W E and Sanecki, J E and Shack, W J and Soppet, W K},
abstractNote = {This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) during the six months from October 1993 to March 1994. EAC and fatigue of piping, pressure vessels, and core components in LWRs are important concerns in operating plants and as extended reactor lifetimes are envisaged. Topics that have been investigated include (a) fatigue of low-alloy steel used in piping, steam generators, and reactor pressure vessels, (b) EAC of wrought and cast austenitic stainless steels (SSs), and (c) radiation-induced segregation and irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS after accumulation of relatively high fluence. Fatigue tests have been conducted on A302-Gr B low-alloy steel to verify whether the current predictions of modest decreases of fatigue life in simulated pressurized water reactor water are valid for high-sulfur heats that show environmentally enhanced fatigue crack growth rates. Additional crack growth data were obtained on fracture-mechanics specimens of austenitic SSs to investigate threshold stress intensity factors for EAC in high-purity oxygenated water at 289{degrees}C. The data were compared with predictions based on crack growth correlations for wrought austenitic SS in oxygenated water developed at ANL and rates in air from Section XI of the ASME Code. Microchemical and microstructural changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating boiling water reactors were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements, which are not specified in the ASTM specifications, may contribute to IASCC of solution-annealed materials.},
doi = {10.2172/45615},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {3}
}