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Irradiation assisted stress corrosion cracking of controlled purity 304L stainless steels (1993)

Abstract

The effect of chromium, phosphorus, silicon and sulfur on the stress corrosion cracking of 304L stainless steel in CERT tests in high purity water or argon at 288[deg]C following irradiation with 3.4 MeV protons at 400[deg]C to 1 dpa, has been investigated using ultrahigh purity alloys (UHP) with controlled impurity additions. Grain boundary segregation of phosphorus or silicon due to proton irradiation was quantified using both Auger electron spectroscopy and scanning transmission electron microscopy, and the alloys with impurity element additions were observed to have greater grain boundary chromium depletion and nickel enrichment than the UHP alloy. The UHP alloy suffered severe cracking in CERT tests in water. Less cracking was found after CERT test of irradiated UHP+Por UHP+Si alloys, despite greater chromium depletion. This suggests a mitigating effect of phosphorus and silicon at grain boundaries. No cracking was found in argon tests, eliminating a purely mechanical embrittlement mechanism, but not eliminating a contribution from radiation hardening. Implanted hydrogen was not a factor in the intergranular cracking found.. Peer Reviewed. http://deepblue.lib.umich.edu/bitstream/2027.42/30754/1/0000404.pdf

Publication details

Download	, http://www.sciencedirect.com/science/article/B6TXN-48053PH-16/2/944b7b347507cadefac5b64d30c9649b http://hdl.handle.net/2027.42/30754 http://dx.doi.org/10.1016/0022-3115(93)90034-V
Publisher	Elsevier
Contributors	Department of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USA, Department of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USA, Department of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USA, Department of Nuclear Engineering The University of Michigan, Ann Arbor, MI 48109, USA, Departmennt of Nuclear Engineering and Department of Materials Science and Engineering, The University of Michigan, Ann Arbor, MI 48109, USA
Repository	University of Michigan (United States)
Keywords	Nuclear Engineering and Radiological Sciences, Engineering
Language	English

Cited publications (1)

Surface modification of alloy in high temperature oxidation /--by Chi-Hua Yang. (1986)

Yang, Chi-Hua.