Hao-Xuan Huang , Yu-Hao Li , Tian-Ren Yang , Hong-Bo Zhou , Jin-Liang Li , Hui-Zhi Ma , Yu-Ze Niu , Xiao-Chun Li , Huiqiu Deng , Guang-Hong Lu
{"title":"Investigating the synergistic evolution of H and He with irradiation defects in Fe by a new Fe-H-He ternary potential","authors":"Hao-Xuan Huang , Yu-Hao Li , Tian-Ren Yang , Hong-Bo Zhou , Jin-Liang Li , Hui-Zhi Ma , Yu-Ze Niu , Xiao-Chun Li , Huiqiu Deng , Guang-Hong Lu","doi":"10.1016/j.jnucmat.2025.155687","DOIUrl":null,"url":null,"abstract":"<div><div>It has been demonstrated that the synergistic effect of hydrogen (H) and helium (He) has a significant promoting effect on the nucleation antungstend growth of irradiation defects, leading to severe deterioration of material performance. In order to explore the synergistic evolution behaviors of H and He with irradiation defects in iron (Fe), we have developed a new Fe-H-He ternary potential through systematic fitting and optimization. During the processes, the interaction between H and He with vacancies and interstitial defects is given prominent consideration. Based on the present potential, we further explored the cooperative evolution behaviors of H-He-void complexes. On the one hand, it is clearly observed that both H and He perfectly form a typical core-shell structure in nanovoids with He inside and H outside, which is consistent with experimental observation. The number of H atoms trapped by He-void complexes will decrease with the increasing of He/V ratios, which is due to the repulsion between H and He. On the other hand, the presence of He-void complexes has a significant promoting effect on the formation of H platelets in Fe. The stress field generated by He-void complexes facilitates the aggregation and initial formation of H platelets, and its range expands as H aggregates, ultimately resulting in the formation of H platelets. The high H concentrations are required to form H platelets at high temperature. More importantly, the formation of H platelets can induce a transition in the local Fe lattice from body-centered cubic to face-centered cubic, indicating a substantial impact on the microstructure and properties of Fe. Consequently, the new Fe-H-He potential provides a powerful tool for exploring the synergistic evolution of H-He-defects and evaluating the performance of Fe in fusion devices.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155687"},"PeriodicalIF":3.2000,"publicationDate":"2025-02-07","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/S0022311525000820","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0
Abstract
It has been demonstrated that the synergistic effect of hydrogen (H) and helium (He) has a significant promoting effect on the nucleation antungstend growth of irradiation defects, leading to severe deterioration of material performance. In order to explore the synergistic evolution behaviors of H and He with irradiation defects in iron (Fe), we have developed a new Fe-H-He ternary potential through systematic fitting and optimization. During the processes, the interaction between H and He with vacancies and interstitial defects is given prominent consideration. Based on the present potential, we further explored the cooperative evolution behaviors of H-He-void complexes. On the one hand, it is clearly observed that both H and He perfectly form a typical core-shell structure in nanovoids with He inside and H outside, which is consistent with experimental observation. The number of H atoms trapped by He-void complexes will decrease with the increasing of He/V ratios, which is due to the repulsion between H and He. On the other hand, the presence of He-void complexes has a significant promoting effect on the formation of H platelets in Fe. The stress field generated by He-void complexes facilitates the aggregation and initial formation of H platelets, and its range expands as H aggregates, ultimately resulting in the formation of H platelets. The high H concentrations are required to form H platelets at high temperature. More importantly, the formation of H platelets can induce a transition in the local Fe lattice from body-centered cubic to face-centered cubic, indicating a substantial impact on the microstructure and properties of Fe. Consequently, the new Fe-H-He potential provides a powerful tool for exploring the synergistic evolution of H-He-defects and evaluating the performance of Fe in fusion devices.
研究表明,氢(H)和氦(He)的协同作用对辐照缺陷的成核和生长有显著的促进作用,导致材料性能严重恶化。为了探索H和He在铁(Fe)辐照缺陷下的协同演化行为,我们通过系统拟合和优化,建立了新的Fe-H-He三元势。在此过程中,重点考虑了H和He与空位和间隙缺陷的相互作用。在此基础上,进一步探讨了h - he -空穴配合物的协同演化行为。一方面,我们清楚地观察到H和He在纳米孔洞中完美地形成了He内H外的典型核壳结构,这与实验观察结果一致。随着He/V比的增加,被He-空穴配合物捕获的H原子数量会减少,这是由于H和He之间的排斥作用所致。另一方面,He-void复合物的存在对铁中H血小板的形成有显著的促进作用。He-void配合物产生的应力场有利于H血小板的聚集和初始形成,随着H的聚集,应力场范围扩大,最终导致H血小板的形成。在高温下形成H型血小板需要高浓度的H。更重要的是,H血小板的形成可以诱导局部铁晶格从体心立方到面心立方的转变,这表明对铁的微观结构和性能有实质性的影响。因此,新的Fe- h - he势为探索h - he缺陷的协同演化和评价熔合装置中Fe的性能提供了有力的工具。
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.