Neutron irradiation response of explosion-welded CuCrZr/316LN joints for ITER application

Xiaoou Yi, Yufeng Du, Yihang Li, Wentuo Han, Pingping Liu, Kenta Yoshida, Takeshi Toyama, Jiming Chen, Qian Zhan, Farong Wan, Somei Ohnuki, Yasuyoshi Nagai

Research output: Contribution to journalArticlepeer-review

1 Citation (Scopus)

Abstract

Explosion-welded CuCrZr/316LN joints, which serve as key joining components in enhanced-heat-flux type first wall panels of ITER, have been neutron irradiated in the BR2 reactor (Belgium) at <190 °C, up to 0.3 dpa. The joints have maintained good structural integrity after irradiation and were free of void swelling. Radiation defects featuring black-spot contrasts were produced on both sides of the CuCrZr/316LN interface. They were on the order of 1022 m−3 in number density and all less than 4 nm in average size. Radiation-enhanced diffusion might have favoured the dissolution of interlayers which were characteristic of pristine CuCrZr/316LN joints, and accelerated the diffusion of key elements (e.g. Cu, Fe) across the interface. The joint interface experienced an increase of Vickers hardness by ~ 21% (∆Hv = 48) after neutron irradiation. Heat treatments of 500 °C/1 h resulted in moderate softening of the interface, while 800 °C/1 h gave rise to a complete elimination of irradiation-induced hardening effect, respectively.

Original languageEnglish
Article number112620
JournalFusion Engineering and Design
Volume169
DOIs
Publication statusPublished - 2021 Aug

Keywords

  • CuCrZr/316LN
  • Explosion welding
  • Mechanical properties
  • Microstructure
  • Neutron irradiation

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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