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Stress corrosion cracking susceptibility of irradiated Type 304 stainless steels [electronic resource].

Published
Rockville, Md. : U.S. Nuclear Regulatory Commission, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
19 pages : digital, PDF file
Additional Creators
Argonne National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Slow-strain-rate tensile tests and microstructural analysis by Auger electron spectroscopy were conducted on specimens of high- and commercial-purity (HP and CP) heats of Type 304 stainless steel obtained from neutron absorber tubes and a control blade sheath after irradiation up to 2.5 × 10{sup 2l} n·cm{sup −2} (E > l MeV) in boiling water reactors (BWRs). The susceptibility of the HP absorber tubes to intergranular stress corrosion cracking (IGSCC) was higher than that of the CP absorber tubes or the CP control blade sheath. IGSCC susceptibilities of the BWR components could not be correlated to segregation impurities on grain boundaries. However for comparable fluence levels, Cr on grain-boundaries.
Report Numbers
E 1.99:anl/mct/cp--74743
E 1.99: conf-9206282--2
conf-9206282--2
anl/mct/cp--74743
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
08/01/1992.
"anl/mct/cp--74743"
" conf-9206282--2"
"DE93003005"
16. ASTM international symposium on the effects of radiation on materials(ISERM),Aurora, CO (United States),23-25 Jun 1992.
Kassner, T.F.; Ruther, W.E.; Chung, H.M.; Sanecki, J.E.
Funding Information
W-31109-ENG-38
View MARC record | catkey: 14458736