Irradiation damages of structural materials under different irradiation environments
Irradiation damages of structural materials under different irradiation environments
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DOI：
10.1016/j.jnucmat.2020.152503
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发表时间：
2021
影响因子：
3.1
通讯作者：
E. Wakai;S. Takaya;Yoshinori Matsui;Y. Nagae;S. Kato;T. Suzudo;M. Yamaguchi;K. Aoto;S. Nogami;A. Hasegawa;H. Abe;Koichi Sato;T. Ishida;S. Makimura;P. Hurh;K. Ammigan;D. Senor;A. Casella;David Edwards
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文献类型：
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作者：
E. Wakai;S. Takaya;Yoshinori Matsui;Y. Nagae;S. Kato;T. Suzudo;M. Yamaguchi;K. Aoto;S. Nogami;A. Hasegawa;H. Abe;Koichi Sato;T. Ishida;S. Makimura;P. Hurh;K. Ammigan;D. Senor;A. Casella;David Edwards
为了推进和发展用于重辐照环境的核系统，如聚变DEMO反应堆、裂变反应堆、快堆、加速器驱动靶系统等，有必要充分了解辐照引起的材料力学性能和其他性能的变化，阐明位移损伤和氦生成的协同效应。本研究主要研究了316FR和304奥氏体不锈钢和HCM12A铁素体/马氏体钢在JRR-3M和/或JOYO快堆中550℃左右辐照后的力学性能变化和微观组织发展。在550℃时，316FR钢的延展性和抗辐照强度都优于304钢。值得注意的是，在550℃和室温下，316FR钢的断裂强度显著提高。结果表明，氦原子对辐照奥氏体不锈钢316FR的蠕变寿命有较大影响。在0.01 ~ 1 appm范围内，蠕变破裂时间比Miyaji等研究的下限略低。蠕变断裂时间折减比的下限（辐照试样与未辐照试样）并没有随着氦产量在10 appm以上至33 appm左右而线性降低。Dpa增强了蠕变寿命的降低。从辐照损伤和材料发展的角度，介绍了辐照环境下高能加速器驱动靶系统的最新研究进展，并讨论了辐射协同下正在研究的具有极高纳米级析出物数密度的钛合金等高耐辐射材料。
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 550oC in JRR-3M reactor and/or JOYO fast reactor. At 550°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 °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.