{"title":"Molecular dynamics simulation of retention and bubble formation in tungsten with carbon impurities under high flux deuterium irradiation","authors":"Yuan Xiang, Liqun Shi, Bin Zhang","doi":"10.1016/j.jnucmat.2024.155576","DOIUrl":null,"url":null,"abstract":"<div><div>W is a critical plasma-facing material in fusion reactors. However, extreme conditions subject W to high-flux D plasma irradiation, resulting in D retention and bubble formation. Importantly, C impurities in the plasma can have a complex effect on D behavior in the W. Due to experimental limitations, the impact of C on the evolution of irradiated W and the underlying mechanisms remains poorly understood. In this study, we employ molecular dynamics simulations to investigate the effects of C on the retention of D in W. The introduction forms of C include irradiation and direct doping. First, Irradiation can cause C to be retained, at the same time, the structure of W is severely damaged. W atoms in the subsurface are bombarded and displaced to form interstitial atoms and even be sputtered out of the W matrix. Statistical results show that the sputtering of W is primarily determined by the energy of impact C, with temperature having relatively minor effects. C irradiation forms a W-C mixed layer on the W surface. This layer has a disordered structure and is mixed with self-interstitial atoms and C atoms. D atoms incident from above are easily intercepted and captured by this layer and are difficult to migrate deeper. Second, C randomly doped in W significantly promotes the retention of D. The higher the C content, the higher the retention rate. Furthermore, the supersaturated accumulation of retained D leads to the formation of D bubbles. D undergoes an evolutionary process of forming molecules, clusters, and finally D bubbles. This work provides new insights into the W-C-D interaction mechanisms in fusion reactors, offering important theoretical support for the selection of W as a plasma-facing material.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"605 ","pages":"Article 155576"},"PeriodicalIF":3.2000,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311524006779","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2024/12/20 0:00:00","PubModel":"Epub","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0
Abstract
W is a critical plasma-facing material in fusion reactors. However, extreme conditions subject W to high-flux D plasma irradiation, resulting in D retention and bubble formation. Importantly, C impurities in the plasma can have a complex effect on D behavior in the W. Due to experimental limitations, the impact of C on the evolution of irradiated W and the underlying mechanisms remains poorly understood. In this study, we employ molecular dynamics simulations to investigate the effects of C on the retention of D in W. The introduction forms of C include irradiation and direct doping. First, Irradiation can cause C to be retained, at the same time, the structure of W is severely damaged. W atoms in the subsurface are bombarded and displaced to form interstitial atoms and even be sputtered out of the W matrix. Statistical results show that the sputtering of W is primarily determined by the energy of impact C, with temperature having relatively minor effects. C irradiation forms a W-C mixed layer on the W surface. This layer has a disordered structure and is mixed with self-interstitial atoms and C atoms. D atoms incident from above are easily intercepted and captured by this layer and are difficult to migrate deeper. Second, C randomly doped in W significantly promotes the retention of D. The higher the C content, the higher the retention rate. Furthermore, the supersaturated accumulation of retained D leads to the formation of D bubbles. D undergoes an evolutionary process of forming molecules, clusters, and finally D bubbles. This work provides new insights into the W-C-D interaction mechanisms in fusion reactors, offering important theoretical support for the selection of W as a plasma-facing material.
钨是聚变反应堆中重要的等离子体面材料。然而,极端条件使W受到高通量D等离子体照射,导致D滞留和气泡形成。重要的是,等离子体中的C杂质可以对W中的D行为产生复杂的影响,由于实验限制,C对辐照W演变的影响及其潜在机制仍然知之甚少。在本研究中,我们采用分子动力学模拟来研究C对w中D保留的影响。C的引入形式包括辐照和直接掺杂。首先,辐照会使C保留,同时W的结构受到严重破坏。地下的W原子被轰击移位形成间隙原子,甚至溅射出W基体。统计结果表明,W的溅射主要由撞击C的能量决定,温度的影响相对较小。C辐照在W表面形成W-C混合层。该层结构无序,由自间隙原子和C原子混合而成。从上面入射的D原子很容易被该层截获和捕获,并且很难向深处迁移。其次,C随机掺杂W中,显著促进d的保留,C含量越高,保留率越高。此外,残留D的过饱和积累导致D气泡的形成。D经历了一个形成分子、团簇、最后形成气泡的进化过程。本研究为聚变反应堆中W- c - d相互作用机理提供了新的见解,为选择W作为等离子体表面材料提供了重要的理论支持。
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.