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Effect of Fe11+ ion combined with helium and deuterium plasmas irradiation on the transient thermal shock behaviors of pure and potassium-doped tungsten  ( EI收录)  

文献类型:期刊文献

英文题名:Effect of Fe11+ ion combined with helium and deuterium plasmas irradiation on the transient thermal shock behaviors of pure and potassium-doped tungsten

作者:Ma, Xiaolei[1]; Feng, Fan[2]; Zhang, Xiaoxin[1]; Wang, Ting[3]; Liu, Xiang[2]; Lv, Wei[4]; Lang, Shaoting[5]; Ge, Changchun[1]; Yan, Qingzhi[1]

第一作者:Ma, Xiaolei

机构:[1] School of Materials Science and Engineering, Institute of Nuclear Materials, University of Science and Technology Beijing, Beijing, 100083, China; [2] Southwestern Institute of Physics, Sichuan, Chengdu, 610041, China; [3] School of Physics, Beihang University, Beijing, 100191, China; [4] Institute of Energy Power Innovation, North China Electric Power University, Beijing, 102206, China; [5] Mechanical and Electrical Engineering, Xinxiang University, Henan, Xinxiang, 453000, China

第一机构:School of Materials Science and Engineering, Institute of Nuclear Materials, University of Science and Technology Beijing, Beijing, 100083, China

通讯机构:[1]School of Materials Science and Engineering, Institute of Nuclear Materials, University of Science and Technology Beijing, Beijing, 100083, China

年份:2023

卷号:573

外文期刊名:Journal of Nuclear Materials

收录:EI(收录号:20224413025913);Scopus(收录号:2-s2.0-85140575136)

语种:英文

外文关键词:Binary alloys - Cracks - Deuterium - Experimental reactors - Helium - Powder metallurgy - Tokamak devices - Tungsten

摘要:The large-scale warm-rolled pure tungsten (PW) and hot-rolled potassium-doped tungsten (W-K) plates were prepared by powder metallurgy technology to meet the demands of International Thermonuclear Experimental Reactor (ITER) in engineering application. In order to evaluate the performance of plasma-facing materials (PFM) in a more realistic service environment as much as possible, the influence of combined irradiation effects of high-energy iron (Fe) ion, deuterium (D) and helium (He) plasmas on the transient thermal shock behavior in the PW and W-K was investigated. The results indicate that the PW can generate more vacancy- and dislocation-type defects than that of W-K after irradiation. The cracking thresholds for un-irradiated PW and W-K are >0.66 and 0.44–0.55 GW/m2, respectively. However, the cracking threshold for both samples decreased to 0.22–0.33 GW/m2 after combined irradiation, indicating that the combined irradiation can significantly reduce the thermal shock resistance of PW and W-K. In addition, according to the statistical results of the crack density and width on the surface of irradiated samples, irradiated W-K owns better thermal shock resistance than irradiated PW under the same thermal shock condition. These results were also verified by the determination of residual stresses. Besides, the relationship between the evolution of irradiation-induced defects and K bubbles is also discussed in detail. These studies can provide an important reference for the identification of future PFM and numerical simulation under combined irradiation plus high thermal load. ? 2022 Elsevier B.V.

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