Hydrogen diffusion layer within solid-state lithium target for compact accelerator-driven neutron source: Irradiation damage, hydrogen concentration, thermal properties and fabrication

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-08-04 DOI:10.1016/j.anucene.2025.111781

Yupeng Xie , Xiaobo Li , Fanxi Zhang , Yaocheng Hu , Yixin Si , Xuanyu Meng , Qiuyu Sun , Yaru Wang , Chen Chen , Xiaozhi Zhang , Sheng Wang

{"title":"Hydrogen diffusion layer within solid-state lithium target for compact accelerator-driven neutron source: Irradiation damage, hydrogen concentration, thermal properties and fabrication","authors":"Yupeng Xie , Xiaobo Li , Fanxi Zhang , Yaocheng Hu , Yixin Si , Xuanyu Meng , Qiuyu Sun , Yaru Wang , Chen Chen , Xiaozhi Zhang , Sheng Wang","doi":"10.1016/j.anucene.2025.111781","DOIUrl":null,"url":null,"abstract":"<div><div>This study focused on investigation of the hydrogen diffusion layer (H-D layer) in the solid-state lithium target for compact accelerator-driven neutron source through numerical simulation and experimental results. Simulations based on Monte Carlo and finite element method were employed to explore the influence of H-D layers (tantalum and vanadium) on the irradiation damage resistance and cooling performance of the solid-state lithium target. For cooling performance, the multi-channel target design with a 1 mm channel width and 47 channels, coupled with an H-D layer, demonstrated the best cooling efficiency. Fabrication of the H-D layer involved depositing a 20 μm Ta layer on a Cu substrate by magnetron sputtering at a power of 300 W, exhibiting excellent surface properties with the lowest surface roughness of 13.9 nm, and a dominant β-phase structure as identified by XRD. Additionally, the influence of the Ta film structure and sputtering power on thermal conductivity was analyzed.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"225 ","pages":"Article 111781"},"PeriodicalIF":2.3000,"publicationDate":"2025-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925005985","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

This study focused on investigation of the hydrogen diffusion layer (H-D layer) in the solid-state lithium target for compact accelerator-driven neutron source through numerical simulation and experimental results. Simulations based on Monte Carlo and finite element method were employed to explore the influence of H-D layers (tantalum and vanadium) on the irradiation damage resistance and cooling performance of the solid-state lithium target. For cooling performance, the multi-channel target design with a 1 mm channel width and 47 channels, coupled with an H-D layer, demonstrated the best cooling efficiency. Fabrication of the H-D layer involved depositing a 20 μm Ta layer on a Cu substrate by magnetron sputtering at a power of 300 W, exhibiting excellent surface properties with the lowest surface roughness of 13.9 nm, and a dominant β-phase structure as identified by XRD. Additionally, the influence of the Ta film structure and sputtering power on thermal conductivity was analyzed.

查看原文本刊更多论文

紧凑加速器驱动中子源固态锂靶内的氢扩散层：辐照损伤、氢浓度、热性能和制造

本研究通过数值模拟和实验结果对紧凑加速器驱动中子源固态锂靶中的氢扩散层（H-D层）进行了研究。采用蒙特卡罗模拟和有限元方法，探讨了H-D层（钽和钒）对固态锂靶材耐辐照损伤和冷却性能的影响。在冷却性能方面，1 mm通道宽度和47个通道的多通道靶设计，加上H-D层，显示出最佳的冷却效率。在300 W的磁控溅射下，在Cu衬底上沉积了一层20 μm的Ta层，其表面粗糙度最低为13.9 nm，具有优异的表面性能，并通过XRD鉴定了其主要的β相结构。此外，还分析了Ta膜结构和溅射功率对导热系数的影响。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.