Irradiation damages of structural materials under different irradiation environments

JOURNAL OF NUCLEAR MATERIALS

卷:543

Article

Wakai, Eiichi^1,2  Takaya, Shigeru³  Matsui, Yoshinori³  Nagae, Yuji⁴  Kato, Shoichi³  Suzudo, Tomoaki^1,5  Yamaguchi, Masataka¹  Aoto, Kazumi⁶  Nogami, Shuhei⁷  Hasegawa, Akira⁷  Abe, Hiroaki⁸  Sato, Koichi⁹  Ishida, Taku^2,10  Makimura, Shunsuke^2,10  Hurh, Patrick G.¹¹  Ammigan, Kavin¹¹  Senor, David J.¹²  Casella, Andrew M.¹²  Edwards, Danny J.¹² 

[1] Japan Atom Energy Agcy, 2-4 Shirakata, Ibaraki 3191195, Japan

[2] J PARC Ctr, Ibaraki 3191195, Japan

[3] Japan Atom Energy Agcy, Ibaraki 3111393, Japan

[4] Japan Atom Energy Agcy, Fukushima 9791151, Japan

[5] Tohoku Univ, Oarai Ctr, Inst Mat Res, 2145-2 Narita Cho, Oarai, Ibaraki 3111313, Japan

[6] Japan Atom Energy Agcy, Tokyo 1008577, Japan

[7] Tohoku Univ, Grad Sch Engn, Dept Quantum Sci & Energy Engn, Aoba Ku, 6-6-01-2 Aramaki Aza Aoba, Sendai, Miyagi 9808579, Japan

[8] Univ Tokyo, Ibaraki 3191188, Japan

[9] Kagoshima Univ, Grad Sch Sci & Engn, Kagoshima 8900065, Japan

[10] High Energy Accelerator Res Org KEK, Tsukuba, Ibaraki 3050801, Japan

[11] Fermilab Natl Accelerator Lab, Batavia, IL 60510 USA

[12] Pacific Northwest Natl Lab, Richland, WA 99352 USA

关键词: Helium;    dpa;    irradiation hardening;    Irradiation creep;    Swelling;    316FR;    HCM12A;    304;   

DOI  :  10.1016/j.jnucmat.2020.152503

来源: Elsevier

【 摘 要 】

For the advancement and development of nuclear systems used in heavy irradiation environments such as fusion DEMO reactors, fission reactors, fast reactors, and accelerator driven target systems, it is necessary to fully understand the changes of mechanical properties and the other properties of the materials induced by irradiation and to clarify the synergistic effect of displacement damage and helium generation. In this study the mechanical property changes and microstructural development induce by displacement damage and helium production have been mainly examined in austenitic stainless steels, 316FR and type304, and ferritic/martensitic steel, HCM12A, irradiated at around 550 oC in JRR-3M reactor and/or JOYO fast reactor. At 550 degrees C, 316FR steel was superior to 304 steel in terms of the amount of ductility and strength with respect to irradiation resistance. It is noteworthy that at 550 degrees C as well as room temperature, the higher fracture strength of the 316FR steels is a remarkable result. It is found that helium atoms strongly influenced on creep lifetime of the irradiated austenitic stainless steel, 316FR. It was found that the ratio of creep rupture time is slightly lower than the lower limit of previous study's Miyaji and co-workers in the region from 0.01 appm to 1 appm. It is also found that the lower limit of reduction ratio of creep rupture time (irradiation specimen to unirradiation one) does not decrease linearly with the helium production above 10 appm up to about 33 appm. dpa enhanced the reduction of creep lifetime. Recent R&D of high-energy accelerator driven target systems used under heavy irradiation environment is also introduced and discussed for high radiation resistance materials such as Ti alloys with very high number density of nano size precipitate, which have been studying under RaDIATE collaboration, from points of view of irradiation damage and materials development. (C) 2020 Elsevier B.V. All rights reserved.

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