Radiation hardening effects on localized deformation and stress corrosion cracking of stainless steels

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Radiation hardening in austenitic stainless steels modifies deformation characteristics and correlate well with increased susceptibility to intergranular stress corrosion cracking (IGSCC). Available data on neutron-irradiated materials have been analyzed and correlations developed between fluence, yield strength, and cracking susceptibility in high-temperature water environments. Large heat-to-heat differences in critical fluence (0.2 to 2.5 {times} 10{sup 21} n/cm{sup 2}) for IGSCC are documented. In many cases, this variability is consistent with yield strength differences among irradiated materials. IGSCC correlates better to yield strength than to fluence for most heats suggesting a possible role of radiation-induced hardening (and microstructure) on cracking. Microstructural evolution ... continued below

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9 p.

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Bruemmer, S. M.; Cole, J. I.; Brimhall, J. L.; Carter, R. D. & Was, G. S. August 1, 1993.

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  • Pacific Northwest Laboratory
    Publisher Info: Pacific Northwest Lab., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Description

Radiation hardening in austenitic stainless steels modifies deformation characteristics and correlate well with increased susceptibility to intergranular stress corrosion cracking (IGSCC). Available data on neutron-irradiated materials have been analyzed and correlations developed between fluence, yield strength, and cracking susceptibility in high-temperature water environments. Large heat-to-heat differences in critical fluence (0.2 to 2.5 {times} 10{sup 21} n/cm{sup 2}) for IGSCC are documented. In many cases, this variability is consistent with yield strength differences among irradiated materials. IGSCC correlates better to yield strength than to fluence for most heats suggesting a possible role of radiation-induced hardening (and microstructure) on cracking. Microstructural evolution during proton and heavy-ion irradiation has been characterized in low-carbon 302SSs. Hardening results from dislocation loops. SEM and TEM are used to examine dose, strain, and temperature effects on deformation. This hardened microstructure produces inhomogeneous planar deformation within the matrix. Regularly spaced steps are created at the surface during deformation which increase in number with increasing macroscopic strain. Twinning is the dominant deformation mechanism at low temperature, while dislocation channeling is observed at 288C. Deformation characteristics are discussed in terms of potential impact on IGSCC.

Physical Description

9 p.

Notes

INIS; OSTI as DE94004308; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

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  • 6. international symposium on environmental degradation of materials in nuclear power systems: water reactors,San Diego, CA (United States),1-5 Aug 1993

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  • Other: DE94004308
  • Report No.: PNL-SA--21725
  • Report No.: CONF-930825--14
  • Grant Number: AC06-76RL01830
  • Grant Number: FG02-93ER12130
  • Office of Scientific & Technical Information Report Number: 10108251
  • Archival Resource Key: ark:/67531/metadc1279612

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  • August 1, 1993

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  • Oct. 12, 2018, 6:44 a.m.

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  • Nov. 15, 2018, 8:26 p.m.

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Bruemmer, S. M.; Cole, J. I.; Brimhall, J. L.; Carter, R. D. & Was, G. S. Radiation hardening effects on localized deformation and stress corrosion cracking of stainless steels, article, August 1, 1993; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1279612/: accessed March 21, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.