Pre-irradiation effect on deuterium retention after high-flux plasma exposure at two temperatures

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-10-15 DOI:10.1016/j.jnucmat.2025.156229

Meng-Qi Zhang , Hao Yin , Yi-Wen Sun , Xiu-Li Zhu , Long Cheng , Yue Yuan , Guang-Hong Lu

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引用次数: 0

Abstract

The effects of 3.5 MeV iron (Fe¹³⁺) ions pre-irradiation on deuterium (D) retention and blistering in recrystallized tungsten were investigated after exposure to low-energy (40 eV) and high-flux (1.8 × 10²² D m⁻² s⁻¹) D plasma at two temperatures (480 K and 630 K) with the high fluence of 2.6 × 10²⁶ m⁻². Surface observations showed a high density of small intragranular blisters on the pristine sample and sparse blisters on pre-irradiated samples at 480 K exposure, while severe surface blisters with maximum sizes reaching several tens of micrometers are present on both pristine and pre-irradiated samples at 630 K exposure. Thermal desorption spectra (TDS) of D indicate different types and amounts of D traps formed in the target sample between the two plasma exposures. Additional high-temperature desorption peaks located above 950 K are present in the TDS of both pristine and pre-irradiated samples at 630 K exposure. Large vacancy clusters are supposed to be trapping sites for the high-temperature desorbed D, and they are most likely the result of the evolution of blistering-induced defects. Total D retention calculation indicates that the pre-irradiation enhances D retention at 480 K exposure, but reduces it at 630 K exposure, suggesting a reversal of the enhancement effect at the higher temperature of 630 K. Since the high-temperature desorption region (900–1100 K) accounts for approximately 80 % of the total D retention—and D desorption in this region is higher in the pristine sample—the reversed enhancement effect is primarily attributed to the source of the high-temperature desorption, namely, large vacancy clusters formed by the evolution of blistering-induced defects. This interpretation is supported by blistering observations, where pre-irradiation suppressed surface blistering and thereby reduced associated defects and large vacancy clusters. This work further reveals the complex influence of pre-irradiation on D behavior in tungsten.

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两种温度下高通量等离子体辐照后氘潴留的预辐照效应

研究了3.5 MeV铁离子（Fe13+）在低能量（40 eV）和高通量（1.8 × 1022 D m−2 s−1）等离子体（480 K和630 K）和高通量（2.6 × 1026 m−2）下辐照后，对重结晶钨中氘(D)保留和起泡的影响。表面观察显示，在480 K照射下，原始样品上存在高密度的小颗粒内水泡，而在630 K照射下，原始样品和预照射样品上都存在严重的表面水泡，最大尺寸可达数十微米。D的热解吸光谱（TDS）表明，在两次等离子体暴露之间，靶样品中形成了不同类型和数量的D陷阱。在630 K下，原始样品和预辐照样品的TDS中都存在位于950 K以上的额外高温脱附峰。大的空位团簇被认为是高温解吸D的捕获点，它们很可能是起泡诱导缺陷演变的结果。总D保留计算表明，预辐照在480 K时增加了D保留，在630 K时减少了D保留，表明在630 K较高温度下的增强效应相反。由于高温解吸区（900-1100 K）约占总D保留量的80%，并且该区域的D解吸在原始样品中更高，因此反向增强效应主要归因于高温解吸的来源，即由起泡缺陷演化形成的大空位团簇。这种解释得到了起泡观察的支持，其中预辐照抑制了表面起泡，从而减少了相关的缺陷和大空位团簇。这项工作进一步揭示了预辐照对钨中D行为的复杂影响。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.