TY - JOUR
T1 - The status of the Japanese material properties handbook and the challenge to facilitate structural design criteria for DEMO in-vessel components
AU - Nozawa, Takashi
AU - Tanigawa, Hiroyasu
AU - Kojima, Takaki
AU - Itoh, Takamoto
AU - Hiyoshi, Noritake
AU - Ohata, Mitsuru
AU - Kato, Taichiro
AU - Ando, Masami
AU - Nakajima, Motoki
AU - Hirose, Takanori
AU - Reed, Jordan D.
AU - Chen, Xiang
AU - Geringer, Josina W.
AU - Katoh, Yutai
N1 - Publisher Copyright:
© 2021 IAEA, Vienna.
PY - 2021/11
Y1 - 2021/11
N2 - 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.
AB - 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.
KW - DEMO design criteria
KW - attribute guides
KW - materials property handbook
KW - neutron irradiation effects
KW - reduced activation ferritic/martensitic steel
UR - http://www.scopus.com/inward/record.url?scp=85118528862&partnerID=8YFLogxK
U2 - 10.1088/1741-4326/ac269f
DO - 10.1088/1741-4326/ac269f
M3 - Article
AN - SCOPUS:85118528862
SN - 0029-5515
VL - 61
JO - Nuclear Fusion
JF - Nuclear Fusion
IS - 11
M1 - 116054
ER -