首页|In-situ TEM study of the effect of hydrogen-helium ratio on defect characteristics in Fe9Cr1.5W0.4Si F/M steel during H2+& He+simultaneous irradiation

In-situ TEM study of the effect of hydrogen-helium ratio on defect characteristics in Fe9Cr1.5W0.4Si F/M steel during H2+& He+simultaneous irradiation

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The effect of hydrogen and helium interaction,especially H-He ratio,on the irradiation behavior of nu-clear materials has not yet been resolved.However,this is an important basis for evaluating the irra-diation properties of nuclear materials and developing high irradiation resistant materials.Here,30 keV H2+and He+dual beams with four H-He ratios of 0:10,3:10,15:10,and 30:10 were used to irradiate the newly developed Fe9Cr1.5W0.4Si F/M steel in TEM to in-situ study the interaction and ratio effect of hydrogen and helium.The addition of H atoms significantly promoted the nucleation of dislocation loops and bubbles.In the early stage of irradiation,the average size and density of dislocation loops increased with the increase of H-He ratio.Meanwhile,the larger the H-He ratio,the easier it was to form a com-plex dislocation network.Furthermore,the final saturation size of bubbles increased with the increase of H-He ratio.It was first found that the swelling was affected by H concentrations,with high H concentra-tions slowing down the increase in swelling.For a certain irradiation dose,a specific H-He ratio would lead to a swelling peak of Fe9Cr1.5W0.4Si F/M steel.The super-sized bubbles at grain boundaries(GBs)were found after H addition,resulting in a bigger swelling of GBs than the matrix.Both the swelling of the GBs and the matrix show a dependence on the H-He ratio.The current work is of great significance for understanding the interaction between hydrogen and helium in nuclear materials.

Dose ratio effectFerritic-martensitic steelHydrogen & helium synergetic irradiationIn-situ TEM

Dewang Cui、Ziqi Cao、Kun He、Yuanming Li、Xi Qiu、Guang Ran

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College of Energy,Xiamen University,Xiamen 361102,China

Fujian Provincial Nuclear Energy Engineering Technology Research Center,Xiamen 361102,China

Science and Technology on Reactor Fuel and Materials Laboratory,Chengdu 610041,China

Nuclear Power Institute of China,Chengdu 610041,China

Science and Technology on Reactor System Design Technology Laboratory,Chengdu 610041,China

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National Natural science Foundation of ChinaNational Natural science Foundation of ChinaNational Science Fund for Distinguished Young Scholars of China

U19672111197519112225506

2024

材料科学技术(英文版)
中国金属学会 中国材料研究学会 中国科学院金属研究所

材料科学技术(英文版)

CSTPCD
影响因子:0.657
ISSN:1005-0302
年,卷(期):2024.173(6)
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