Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions

Yoshitake, T
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan

Yamagata, I
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan

Akasaka, N
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan

Nakamura, Y
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan

Tsai, H
Energy Technology Division, Argonne National Laboratory, Argonne, IL, Japan

Cole, J
Nuclear Technology Division, Argonne National Laboratory-West, Idaho Falls, ID, Japan

Allen, T
Engineering Physics, College of Engineering, University of Wisconsin-Madison, Madison, WI, Japan

(Received 19 April 2004; accepted 4 November 2004)
JOURNAL JAI
Abstract
The effects of lower strain rate on the tensile behavior of 12 % cold-worked type 316 stainless steels irradiated in the EBR-II reactor under low-dose-rate and moderate temperature conditions were investigated. Tensile tests were carried out at a strain rate of 1×10^-7/s. Post-test fractography and microstructural characterization were also performed. Irradiation temperature and dose appeared to have the greatest effect on hardening and ductility loss, whereas dose rate appeared to have less apparent effects. In conjunction with earlier work performed on the same material at a strain rate of 1×10^-3/s, there was no significant effect of strain rate on tensile behavior under the irradiation conditions examined. For fracture behavior, the material after irradiation exhibited typical ductile fracture during both high and low-strain-rate tests.

Keywords:
ductility, EBR-II reflector duct, embrittlement, fast reactor core materials, irradiation hardening, low strain rate, lower dose rate irradiation, stainless steels, tensile properties, Type 316 stainless steel

Paper ID: JAI12346
DOI: 10.1520/JAI12346

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Author Yoshitake, T Affiliation Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan Author Yamagata, I Affiliation Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan Author Akasaka, N Affiliation Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan Author Nakamura, Y Affiliation Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oarai-machi, Ibaraki, Japan Author Tsai, H Affiliation Energy Technology Division, Argonne National Laboratory, Argonne, IL, Japan Author Cole, J Affiliation Nuclear Technology Division, Argonne National Laboratory-West, Idaho Falls, ID, Japan Author Allen, T Affiliation Engineering Physics, College of Engineering, University of Wisconsin-Madison, Madison, WI, Japan Title: Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions Symposium: Effects of Radiation on Materials: 22nd International Symposium, 2004-6-10
Committee: E10 on Nuclear Technology and Applications