Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

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Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of reactor pressure vessels because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. Experimental data are presented on fracture toughness and crack growth rates (CGRs) of austenitic SSs irradiated to fluence levels up to 2.0 x 10{sup 21} n/cm{sup 2} (E > 1 MeV) ({approx}3.0 dpa) at {approx}288 C. Crack growth tests were conducted under cycling loading and long hold time trapezoidal loading in simulated boiling ... continued below

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104 pages

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Chopra, O. K.; Gruber, E. E. & Shack, W. J. June 25, 2003.

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Description

Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of reactor pressure vessels because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. Experimental data are presented on fracture toughness and crack growth rates (CGRs) of austenitic SSs irradiated to fluence levels up to 2.0 x 10{sup 21} n/cm{sup 2} (E > 1 MeV) ({approx}3.0 dpa) at {approx}288 C. Crack growth tests were conducted under cycling loading and long hold time trapezoidal loading in simulated boiling water reactor (BWR) environments, and fracture toughness tests were conducted in air. Neutron irradiation at 288 C decreases the fracture toughness of the steels; the data from commercial heats fall within the scatter band for the data obtained at higher temperatures. In addition, the results indicate significant enhancement of CGRs of the irradiated steels in normal water chemistry BWR environment; the CGRs for irradiated steels are a factor of {approx}5 higher than the disposition curve proposed for sensitized austenitic SSs. The rates decreased by more than an order of magnitude in low-dissolved-oxygen BWR environment.

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104 pages

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  • Other Information: PBD: 25 Jun 2003

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  • Report No.: ANL-03/22
  • Grant Number: W-31-109-ENG-38
  • DOI: 10.2172/822551 | External Link
  • Office of Scientific & Technical Information Report Number: 822551
  • Archival Resource Key: ark:/67531/metadc788015

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  • June 25, 2003

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  • Dec. 3, 2015, 9:30 a.m.

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  • March 24, 2016, 9:54 p.m.

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Chopra, O. K.; Gruber, E. E. & Shack, W. J. Fracture toughness and crack growth rates of irradiated austenitic stainless steels., report, June 25, 2003; Illinois. (digital.library.unt.edu/ark:/67531/metadc788015/: accessed August 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.