TY - GEN
T1 - The effect of low dose rate irradiation on the swelling of 12% cold-worked 316 stainless steel
AU - Allen, T. R.
AU - Cole, J. I.
AU - Tsai, H.
AU - Ukai, S.
AU - Mizuta, S.
AU - Yoshitake, T.
PY - 1999
Y1 - 1999
N2 - In pressurized water reactor (PWR) and fast reactor components, some structural components made of stainless steel are irradiated at temperatures near 400°C. If large amounts of swelling (>10%) occur in these reactor internals, significant swelling related embrittlement may occur. Although fast reactor studies indicate that swelling should be insignificant at around 400°C, the low dose rate conditions experienced by structural components may possibly lead to significant swelling. To address these issues, JNC and ANL have collaborated to analyze swelling in 12% cold-worked 316 stainless steel, irradiated in the EBR-II reactor at temperatures from 376-444°C, at dose rate between 4.9×10-8 and 5.8×10-7 dpa/s, and to doses of 56 dpa. For these irradiation conditions, the swelling decreases markedly at temperatures less than approximately 386°C, with the extrapolated swelling at 100 dpa being around 3%. For temperatures greater than approximately 386°C, the swelling extrapolated to 100 dpa is around 9%. For a factor of two difference in dose rate, no statistically significant effect of dose rate on swelling was seen. For the range of dose rates analyzed, the swelling measurements do not support significant (>10%) swelling of 316 stainless steel in PWRs.
AB - In pressurized water reactor (PWR) and fast reactor components, some structural components made of stainless steel are irradiated at temperatures near 400°C. If large amounts of swelling (>10%) occur in these reactor internals, significant swelling related embrittlement may occur. Although fast reactor studies indicate that swelling should be insignificant at around 400°C, the low dose rate conditions experienced by structural components may possibly lead to significant swelling. To address these issues, JNC and ANL have collaborated to analyze swelling in 12% cold-worked 316 stainless steel, irradiated in the EBR-II reactor at temperatures from 376-444°C, at dose rate between 4.9×10-8 and 5.8×10-7 dpa/s, and to doses of 56 dpa. For these irradiation conditions, the swelling decreases markedly at temperatures less than approximately 386°C, with the extrapolated swelling at 100 dpa being around 3%. For temperatures greater than approximately 386°C, the swelling extrapolated to 100 dpa is around 9%. For a factor of two difference in dose rate, no statistically significant effect of dose rate on swelling was seen. For the range of dose rates analyzed, the swelling measurements do not support significant (>10%) swelling of 316 stainless steel in PWRs.
UR - https://www.scopus.com/pages/publications/0033489293
U2 - 10.1002/9781118787618.ch108
DO - 10.1002/9781118787618.ch108
M3 - Conference contribution
AN - SCOPUS:0033489293
SN - 0873394755
SN - 9780873394758
T3 - Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
SP - 1035
EP - 1043
BT - Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
A2 - Bruemmer, S.
A2 - Ford, P.
A2 - Was, G.
PB - Minerals, Metals and Materials Society
T2 - Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
Y2 - 1 August 1999 through 5 August 1999
ER -