Embrittlement of chromium alloys after neutron irradiation at high temperatures to damage doses of 10–46 dpa

IF 2.7 2区物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2025-03-01 Epub Date: 2025-01-08 DOI:10.1016/j.nme.2025.101871

Vladimir Chakin , Ramil Gaisin , Carsten Bonnekoh , Michael Duerrschnabel , Michael Rieth , Bronislava Gorr , Mikola Brodnikikovsky , Mikola Krapivka , Sergey Firstov

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Abstract

The study of chromium alloys, including the low-alloyed BX-2 K alloy and Cr-Fe alloys alloyed with Zr, Y, Al, Mn, Mo additions, after irradiation at temperatures ranging from 400 to 1000 °C and neutron fluences of (2.0 − 9.3) × 10²⁶ m⁻² (E > 0.1 MeV), corresponding to damage doses of 10–46 dpa, revealed a significant tendency for radiation embrittlement in all studied alloys. The tensile ductile-to-brittle transition temperature (DBTT) for these alloys increased to 250–700 °C after irradiation, while the initial DBTT was lower than room temperature. To enhance radiation embrittlement resistance, the Cr10FeZrY alloy, which exhibits a minimum DBTT of 250 °C, is recommended as a basis for further improvement of mechanical properties of Cr-Fe alloys under neutron irradiation.

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损伤剂量为10-46 dpa的高温中子辐照后铬合金的脆化

铬合金，包括添加Zr、Y、Al、Mn、Mo的低合金化bx - 2k合金和Cr-Fe合金，在400 ~ 1000℃辐照后（2.0 ~ 9.3）× 1026 m−2 (E >；0.1 MeV)，对应的损伤剂量为10-46 dpa，在所有研究的合金中显示出明显的辐射脆化趋势。辐照后合金的拉伸韧脆转变温度（DBTT）提高到250 ~ 700℃，而初始DBTT低于室温。为了提高抗辐射脆化性能，推荐采用250℃最低DBTT的Cr10FeZrY合金作为进一步提高Cr-Fe合金在中子辐照下力学性能的基础。

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来源期刊

Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)

CiteScore

3.70

自引率

15.40%

发文量

175

审稿时长

20 weeks

期刊介绍： The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.