钼和钼铼合金位移级联的分子动力学模拟

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Xudong Wang , Rongyang Qiu , Yankun Dou , Yangchun Chen , Haipan Xiang , Peng Jiang , Xinfu He , Wen Yang , Guangdong Liu , Huiqiu Deng
{"title":"钼和钼铼合金位移级联的分子动力学模拟","authors":"Xudong Wang ,&nbsp;Rongyang Qiu ,&nbsp;Yankun Dou ,&nbsp;Yangchun Chen ,&nbsp;Haipan Xiang ,&nbsp;Peng Jiang ,&nbsp;Xinfu He ,&nbsp;Wen Yang ,&nbsp;Guangdong Liu ,&nbsp;Huiqiu Deng","doi":"10.1016/j.nme.2024.101804","DOIUrl":null,"url":null,"abstract":"<div><div>Molybdenum-Rhenium (Mo-Re) alloys are considered core materials for advanced nuclear reactor components due to their excellent mechanical properties, machinability, and resistance to irradiation damage. However, irradiation-induced embrittlement and phase precipitation at high temperatures, along with transmutation nuclides, have hindered their broader application. To address this, we developed a Mo-Re interatomic potential using the Finnis-Sinclair formalism, facilitating molecular dynamics simulations to study primary irradiation damage. Systemically primary irradiation damage simulations for Mo and Mo-Re alloys have been performed. It’s found that there were more Frenkel-pair defects produced during the stage of thermal spike in Mo-Re alloys but fewer defects survived at the end of the cascade compared to Mo. In addition, the number of large-size interstitial clusters and dislocation loops was higher in Mo-Re alloys than in pure Mo with the same PKA energy. This is mainly attributed to the fact that Mo-Re alloys have lower thermal conductivity, while the binding energies of interstitial clusters and dislocation loops with sizes less than 100 in Mo-Re alloys are comparable to those of pure Mo, resulting in higher defect composites and larger defect sizes in Mo-Re alloys. These findings provide valuable insights into the primary damage mechanisms in Mo-Re alloys under irradiation, offering a foundation for developing kinetic models to simulate radiation-induced microstructural evolution.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101804"},"PeriodicalIF":2.3000,"publicationDate":"2024-11-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Molecular dynamic simulations of displacement cascades in molybdenum and molybdenum-rhenium alloys\",\"authors\":\"Xudong Wang ,&nbsp;Rongyang Qiu ,&nbsp;Yankun Dou ,&nbsp;Yangchun Chen ,&nbsp;Haipan Xiang ,&nbsp;Peng Jiang ,&nbsp;Xinfu He ,&nbsp;Wen Yang ,&nbsp;Guangdong Liu ,&nbsp;Huiqiu Deng\",\"doi\":\"10.1016/j.nme.2024.101804\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Molybdenum-Rhenium (Mo-Re) alloys are considered core materials for advanced nuclear reactor components due to their excellent mechanical properties, machinability, and resistance to irradiation damage. However, irradiation-induced embrittlement and phase precipitation at high temperatures, along with transmutation nuclides, have hindered their broader application. To address this, we developed a Mo-Re interatomic potential using the Finnis-Sinclair formalism, facilitating molecular dynamics simulations to study primary irradiation damage. Systemically primary irradiation damage simulations for Mo and Mo-Re alloys have been performed. It’s found that there were more Frenkel-pair defects produced during the stage of thermal spike in Mo-Re alloys but fewer defects survived at the end of the cascade compared to Mo. In addition, the number of large-size interstitial clusters and dislocation loops was higher in Mo-Re alloys than in pure Mo with the same PKA energy. This is mainly attributed to the fact that Mo-Re alloys have lower thermal conductivity, while the binding energies of interstitial clusters and dislocation loops with sizes less than 100 in Mo-Re alloys are comparable to those of pure Mo, resulting in higher defect composites and larger defect sizes in Mo-Re alloys. These findings provide valuable insights into the primary damage mechanisms in Mo-Re alloys under irradiation, offering a foundation for developing kinetic models to simulate radiation-induced microstructural evolution.</div></div>\",\"PeriodicalId\":56004,\"journal\":{\"name\":\"Nuclear Materials and Energy\",\"volume\":\"41 \",\"pages\":\"Article 101804\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2024-11-04\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Materials and Energy\",\"FirstCategoryId\":\"101\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S2352179124002278\",\"RegionNum\":2,\"RegionCategory\":\"物理与天体物理\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Materials and Energy","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S2352179124002278","RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

摘要

钼-铼(Mo-Re)合金具有优异的机械性能、机械加工性能和抗辐照损伤性能,因此被认为是先进核反应堆部件的核心材料。然而,辐照诱发的脆性和高温下的相析出以及嬗变核素阻碍了它们的广泛应用。为了解决这个问题,我们利用 Finnis-Sinclair 形式主义开发了一种 Mo-Re 原子间势,便于分子动力学模拟研究原生辐照损伤。我们对 Mo 和 Mo-Re 合金进行了系统的原生辐照损伤模拟。结果发现,Mo-Re 合金在热尖峰阶段产生的 Frenkel 对缺陷较多,但与 Mo 相比,在级联结束时存活的缺陷较少。此外,在 PKA 能量相同的情况下,Mo-Re 合金中大尺寸间隙簇和位错环的数量高于纯 Mo。这主要是由于 Mo-Re 合金的热导率较低,而 Mo-Re 合金中尺寸小于 100 的间隙团簇和位错环的结合能与纯钼相当,从而导致 Mo-Re 合金中的缺陷复合度较高,缺陷尺寸较大。这些发现为了解辐照下 Mo-Re 合金的主要损伤机制提供了宝贵的见解,为开发动力学模型模拟辐照诱导的微结构演变奠定了基础。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Molecular dynamic simulations of displacement cascades in molybdenum and molybdenum-rhenium alloys
Molybdenum-Rhenium (Mo-Re) alloys are considered core materials for advanced nuclear reactor components due to their excellent mechanical properties, machinability, and resistance to irradiation damage. However, irradiation-induced embrittlement and phase precipitation at high temperatures, along with transmutation nuclides, have hindered their broader application. To address this, we developed a Mo-Re interatomic potential using the Finnis-Sinclair formalism, facilitating molecular dynamics simulations to study primary irradiation damage. Systemically primary irradiation damage simulations for Mo and Mo-Re alloys have been performed. It’s found that there were more Frenkel-pair defects produced during the stage of thermal spike in Mo-Re alloys but fewer defects survived at the end of the cascade compared to Mo. In addition, the number of large-size interstitial clusters and dislocation loops was higher in Mo-Re alloys than in pure Mo with the same PKA energy. This is mainly attributed to the fact that Mo-Re alloys have lower thermal conductivity, while the binding energies of interstitial clusters and dislocation loops with sizes less than 100 in Mo-Re alloys are comparable to those of pure Mo, resulting in higher defect composites and larger defect sizes in Mo-Re alloys. These findings provide valuable insights into the primary damage mechanisms in Mo-Re alloys under irradiation, offering a foundation for developing kinetic models to simulate radiation-induced microstructural evolution.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信