Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors

Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
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DOI:
10.1016/j.nme.2018.05.018
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发表时间:
2018-08
影响因子:
2.6
通讯作者:
A. Prasitthipayong;D. Frazer;A. Kareer;M. Abad;A. Garner;B. Jóni;T. Ungár;G. Ribárik;M. Preuss
A. Prasitthipayong;D. Frazer;A. Kareer;M. Abad;A. Garner;B. Jóni;T. Ungár;G. Ribárik;M. Preuss
中科院分区:
物理与天体物理2区
文献类型:
--
作者:
A. Prasitthipayong;D. Frazer;A. Kareer;M. Abad;A. Garner;B. Jóni;T. Ungár;G. Ribárik;M. Preuss

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离子辐照通常用于模拟中子辐照的效应,这是由于材料的活化减少和剂量率大大增加。然而,离子的低穿透深度需要开发小规模的机械测试技术,如纳米压痕和微压缩,以测量辐照材料的机械性能。在这项研究中,几个候选结构合金的第四代反应堆(800 H,T91,纳米晶体T91和14 YWT)与70 MeV的Fe 9+离子在452 °C辐照的平均损伤为20.68 dpa。无论是纳米压痕和微压缩技术揭示了显着的辐照硬化和增加后,在奥氏体800 H和铁素体-马氏体T91合金辐照屈服应力。观察到离子辐照对纳米晶T91和氧化物弥散强化14 YWT的机械性能具有最小的影响。X射线衍射测量的线展宽分析进一步支持了这些观察结果,其显示在辐照后14 YWT和纳米晶T91合金中位错密度的显著较小的增加。此外,观察到良好的协议之间的横截面纳米压痕和SRIM计算的损伤轮廓。
Ion irradiation is often used to simulate the effects of neutron irradiation due to reduced activation of materials and vastly increased dose rates. However, the low penetration depth of ions requires the development of small-scale mechanical testing techniques, such as nanoindentation and microcompression, in order to measure mechanical properties of the irradiated material. In this study, several candidate structural alloys for Gen-IV reactors (800H, T91, nanocrystalline T91 and 14YWT) were irradiated with 70 MeV Fe9+ions at 452 °C to an average damage of 20.68 dpa. Both the nanoindentation and microcompression techniques revealed significant irradiation hardening and an increase in yield stress after irradiation in austenitic 800H and ferritic-martensitic T91 alloys. Ion irradiation was observed to have minimal effect on the mechanical properties of nanocrystalline T91 and oxide dispersion strengthened 14YWT. These observations are further supported by line broadening analysis of X-ray diffraction measurements, which show a significantly smaller increase in dislocation density in the 14YWT and nanocrystalline T91 alloys after irradiation. In addition, good agreement was observed between cross-sectional nanoindentation and the damage profile from SRIM calculations.