Investigation of the thermo-mehcanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory

Research output: Contribution to journalArticle

Authors

Institutes & Expert groups

  • Peking University
  • Shanghai Jiao-Tong University

Documents & links

DOI

Abstract

The thermo-mechanical behavior of non-irradiated (at 223 K, 302 K and 573 K) and neutron irradiated (at 573 K) Fe-2.5Cr, Fe-5Cr and Fe-9Cr alloys is studied by a self-consistent plasticity theory, which consists of constitutive equations describing the contribution of radiation defects at grain level, and the elasticviscoplastic self-consistent method to obtain polycrystalline behaviors. Attention is paid to two types of radiation-induced defects: interstitial dislocation loops and solute rich clusters, which are believed to be the main sources of hardening in Fe-Cr alloys at medium irradiation doses. Both the hardening mechanism and microstructural evolution are investigated by using available experimental data on microstructures, and implementing hardening rules derived from atomistic data. Good agreement with experimental data is achieved for both the yield stress and strain hardening of non-irradiated and irradiated Fe-Cr alloys by treating dislocation loops as strong thermally activated obstacles and solute rich clusters as weak shearable ones.

Details

Original languageEnglish
Pages (from-to)123-133
Number of pages10
JournalJournal of Nuclear Materials
Volume477
DOIs
StatePublished - 15 Aug 2016

Keywords

  • iron alloys, Irradiation effect, defects, continuum mechanics model, mechanical behavior

ID: 2179192