Emulating neutron-induced void swelling in stainless steels using ion irradiation

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Authors

Institutes & Expert groups

  • INL - Idaho national Laboratory
  • TAMU - Texas A&M University
  • LANL - Los Alamos National Laboratory

Abstract

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. © 2019, The Minerals, Metals & Materials Society.

Details

Original languageEnglish
Title of host publicationMinerals, Metals and Materials Series
PublisherSpringer Nature [academic journals on nature.com]
Pages669-680
Number of pages12
Publication statusPublished - Aug 2019
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States
Duration: 18 Aug 201922 Aug 2019
http://www.ans.org/meetings/m_288

Publication series

NameMinerals, Metals and Materials Series
ISSN (Electronic)2367-1181

Conference

Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
CountryUnited States
CityBoston
Period2019-08-182019-08-22
Internet address

Keywords

  • Austenitic stainless steels, Ferritic/martensitic stainless steel, Light water reactors, Self-ion irradiation, Void swelling

ID: 6736765