Journal Published Online: 28 February 2005
Volume 2, Issue 3

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

CODEN: JAIOAD

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.

Author Information

Yoshitake, T
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oaraimachi, Ibaraki, Japan
Yamagata, I
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oaraimachi, Ibaraki, Japan
Akasaka, N
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oaraimachi, Ibaraki, Japan
Nakamura, Y
Fuels and Materials Division, Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Oaraimachi, Ibaraki, Japan
Tsai, H
Energy Technology Division, Argonne National Laboratory, Argonne, IL
Cole, J
Nuclear Technology Division, Argonne National Laboratory-West, Idaho Falls, ID
Allen, T
Engineering Physics, College of Engineering, University of Wisconsin-Madison, Madison, WI
Pages: 12
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Stock #: JAI12346
ISSN: 1546-962X
DOI: 10.1520/JAI12346