TY - GEN
T1 - Emulating neutron-induced void swelling in stainless steels using ion irradiation
AU - Sun, C.
AU - Malerba, L.
AU - Konstantinovic, M. J.
AU - Garner, F. A.
AU - Maloy, S. A.
N1 - Publisher Copyright:
© The Minerals, Metals & Materials Society 2018.
PY - 2018
Y1 - 2018
N2 - Self-ion irradiation is currently being used to explore the relative void swelling resistance of various candidate advanced alloys for a wide variety of nuclear systems, including light water reactor (LWR) reactors. The credibility of using this surrogate irradiation technique to evaluate potential in-reactor behavior requires that certain facets of neutron-induced behavior be reproduced in the ion simulation. Of particular importance is the ability of ion irradiation to produce the anticipated post-transient swelling rates for fcc and bcc iron-base alloys characteristic of reactor irradiation at ~1.0%/dpa and ~0.2%/dpa, respectively. Using a model duplex Fe-9Cr-C alloy irradiated at 450, ℃ with 8, MeV Fe+ ions it is shown in this study that a post-transient rate of ~0.2%/dpa is observed in the ferrite phase after an incubation period of ~60, dpa. It is also shown that the ferrite phase attains this rate first, while the tempered martensite phase exhibits a longer transient delay prior to the onset of high-rate swelling.
AB - Self-ion irradiation is currently being used to explore the relative void swelling resistance of various candidate advanced alloys for a wide variety of nuclear systems, including light water reactor (LWR) reactors. The credibility of using this surrogate irradiation technique to evaluate potential in-reactor behavior requires that certain facets of neutron-induced behavior be reproduced in the ion simulation. Of particular importance is the ability of ion irradiation to produce the anticipated post-transient swelling rates for fcc and bcc iron-base alloys characteristic of reactor irradiation at ~1.0%/dpa and ~0.2%/dpa, respectively. Using a model duplex Fe-9Cr-C alloy irradiated at 450, ℃ with 8, MeV Fe+ ions it is shown in this study that a post-transient rate of ~0.2%/dpa is observed in the ferrite phase after an incubation period of ~60, dpa. It is also shown that the ferrite phase attains this rate first, while the tempered martensite phase exhibits a longer transient delay prior to the onset of high-rate swelling.
KW - Austenitic stainless steel
KW - Ferritic/martensitic stainless steel
KW - Light water reactors
KW - Self-ion irradiation
KW - Void swelling
UR - https://www.scopus.com/pages/publications/85042512560
U2 - 10.1007/978-3-319-67244-1_43
DO - 10.1007/978-3-319-67244-1_43
M3 - Conference contribution
AN - SCOPUS:85042512560
SN - 9783319672434
T3 - Minerals, Metals and Materials Series
SP - 669
EP - 680
BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
A2 - Paraventi, Denise
A2 - Wright, Michael
A2 - Jackson, John H.
PB - Springer International Publishing
T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Y2 - 13 August 2017 through 17 August 2017
ER -