The status of the Japanese material properties handbook and the challenge to facilitate structural design criteria for DEMO in-vessel components

Takashi Nozawa, Hiroyasu Tanigawa, Takaki Kojima, Takamoto Itoh, Noritake Hiyoshi, Mitsuru Ohata, Taichiro Kato, Masami Ando, Motoki Nakajima, Takanori Hirose, Jordan D. Reed, Xiang Chen, Josina W. Geringer, Yutai Katoh

Research output: Contribution to journalArticlepeer-review

18 Scopus citations

Abstract

This paper summarizes the current status of the material properties handbook for a structural design using Japanese reduced-activation ferritic/martensitic steel F82H. Specifically, the key structural parameters, e.g. time-independent/dependent design stresses and fatigue design curves, were determined by following the French structural design code RCC-MRx. Moreover, under the Japan-U.S. collaboration, tensile data were newly added to the benchmark heavy irradiation data up to 80 dpa, as critical input information in the intermediate check and review in Japan. Furthermore, the status of structural material data and the near-term and long-term issues were clarified by the evaluation using the attribute guides. In parallel, the structural design approaches, which were newly introduced and extended to cope with the structural design issues under the complex environmental conditions peculiar to the DEMO reactor, were noted with the initial R and D results. Of the many design issues, the multi-axial loading conditions due to the complexity of the DEMO reactor as well as the coolant compatibility and the irradiation effect are mentioned. For example, in the paper, multi-axial fatigue-creep testing and evaluation using the modified universal slope method and brittle/ductile fracture testing and evaluation using the local approach are explained toward DEMO.

Original languageEnglish
Article number116054
JournalNuclear Fusion
Volume61
Issue number11
DOIs
StatePublished - Nov 2021

Keywords

  • DEMO design criteria
  • attribute guides
  • materials property handbook
  • neutron irradiation effects
  • reduced activation ferritic/martensitic steel

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