Environmentally assisted cracking in light-water reactors: Semi-annual report, January--June 1997. Volume 24

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This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from January 1997 to June 1997. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Types 304 and 304L SS, and (c) EAC of Alloys 600 and 690. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during various portions of a ... continued below

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112 p.

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Chopra, O. K.; Chung, H. M. & Gruber, E. E. April 1998.

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Description

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from January 1997 to June 1997. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Types 304 and 304L SS, and (c) EAC of Alloys 600 and 690. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during various portions of a tensile-loading cycle is equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated boiling water reactor (BWR) water at 288 C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in low-DO, simulated pressurized water reactor environments.

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112 p.

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INIS; OSTI as TI98004909

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  • Other Information: PBD: Apr 1998

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  • Other: TI98004909
  • Report No.: NUREG/CR--4667-Vol.24
  • Report No.: ANL--98/6-Vol.24
  • Grant Number: W-31109-ENG-38
  • DOI: 10.2172/595659 | External Link
  • Office of Scientific & Technical Information Report Number: 595659
  • Archival Resource Key: ark:/67531/metadc697279

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • April 1998

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 8, 2016, 8:05 p.m.

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Chopra, O. K.; Chung, H. M. & Gruber, E. E. Environmentally assisted cracking in light-water reactors: Semi-annual report, January--June 1997. Volume 24, report, April 1998; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc697279/: accessed October 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.