Hui-Zhi Ma, Yu-Hao Li, Yu-Ze Niu, Hong-Bo Zhou, Guang-Hong Lu
{"title":"Modified sink strength model for dislocation in tungsten: Dependence on temperature and probability density distribution","authors":"Hui-Zhi Ma, Yu-Hao Li, Yu-Ze Niu, Hong-Bo Zhou, Guang-Hong Lu","doi":"10.1016/j.nme.2025.101900","DOIUrl":null,"url":null,"abstract":"<div><div>Sink strength, as a fundamental parameter in mean-field approaches, describes the ability of sinks (e.g., dislocation lines) to capture migrating defects and is crucial for simulating the microstructure evolution of irradiation damage in nuclear materials. Here, taking body centered cubic tungsten (W) as an example, we systematically investigate the sink strength of dislocation lines using the object Kinetic Monte Carlo (OKMC) method. It is found that there are noteworthy discrepancies of sink strength between the traditional theoretical expression and OKMC simulations. This should be attributed to two factors, namely temperature and probability density distribution. The former can be derived from a master curve that has already been proposed for 1D to 3D diffusion–reaction kinetics, while the latter can be well described by a modified analytical expression of sink strength for dislocation lines. By incorporating these factors, the discrepancy between theoretical results and OKMC simulations is eliminated. Notably, the results of defect evolution in irradiated W, obtained using the modified sink strength expression, exhibit a greater consistency with experimental observations than those derived from the conventional model. These results provide a better insight into the sink strength model, and have broad implications for understanding and reproducing the microstructure evolution of irradiation defects in materials.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101900"},"PeriodicalIF":2.3000,"publicationDate":"2025-02-16","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/S2352179125000407","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
Abstract
Sink strength, as a fundamental parameter in mean-field approaches, describes the ability of sinks (e.g., dislocation lines) to capture migrating defects and is crucial for simulating the microstructure evolution of irradiation damage in nuclear materials. Here, taking body centered cubic tungsten (W) as an example, we systematically investigate the sink strength of dislocation lines using the object Kinetic Monte Carlo (OKMC) method. It is found that there are noteworthy discrepancies of sink strength between the traditional theoretical expression and OKMC simulations. This should be attributed to two factors, namely temperature and probability density distribution. The former can be derived from a master curve that has already been proposed for 1D to 3D diffusion–reaction kinetics, while the latter can be well described by a modified analytical expression of sink strength for dislocation lines. By incorporating these factors, the discrepancy between theoretical results and OKMC simulations is eliminated. Notably, the results of defect evolution in irradiated W, obtained using the modified sink strength expression, exhibit a greater consistency with experimental observations than those derived from the conventional model. These results provide a better insight into the sink strength model, and have broad implications for understanding and reproducing the microstructure evolution of irradiation defects in materials.
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.