Jinyu Shi , Lina Chen , Yiming Lei , Chenxu Wang , Jie Zhang , Jingyang Wang
{"title":"Irradiation damage of zirconium carbide with different stoichiometry","authors":"Jinyu Shi , Lina Chen , Yiming Lei , Chenxu Wang , Jie Zhang , Jingyang Wang","doi":"10.1016/j.vacuum.2025.114355","DOIUrl":null,"url":null,"abstract":"<div><div>Zirconium carbide (ZrC) has emerged as attractive candidate material for next-generation fission and fusion energy system that are inevitably exposed to extreme irradiation environment. In this work, irradiation induced damage evolution in ZrC<sub>x</sub> (x = 0.55, 0.78, 0.86) induced by 3 MeV Au<sup>2+</sup> irradiation at the fluences ranging from 1 × 10<sup>14</sup> cm<sup>−2</sup> to 2 × 10<sup>16</sup> cm<sup>−2</sup> at room temperature (RT) was systematically investigated. The observations revealed that the radiation tolerance, especially its resistance to amorphization, was sensitive to the stoichiometry. Additionally, local accumulation of carbon vacancies both in the ordered phases and twin interfaces promotes the recombination of irradiation point defects, thereby enhancing the irradiation tolerance of substoichiometric ZrC<sub>x</sub>. This work provides a fundamental understanding of correlation between the stoichiometry and irradiation damage in zirconium carbide.</div></div>","PeriodicalId":23559,"journal":{"name":"Vacuum","volume":"239 ","pages":"Article 114355"},"PeriodicalIF":3.9000,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Vacuum","FirstCategoryId":"88","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0042207X25003458","RegionNum":2,"RegionCategory":"材料科学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/4/21 0:00:00","PubModel":"Epub","JCR":"Q2","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0
Abstract
Zirconium carbide (ZrC) has emerged as attractive candidate material for next-generation fission and fusion energy system that are inevitably exposed to extreme irradiation environment. In this work, irradiation induced damage evolution in ZrCx (x = 0.55, 0.78, 0.86) induced by 3 MeV Au2+ irradiation at the fluences ranging from 1 × 1014 cm−2 to 2 × 1016 cm−2 at room temperature (RT) was systematically investigated. The observations revealed that the radiation tolerance, especially its resistance to amorphization, was sensitive to the stoichiometry. Additionally, local accumulation of carbon vacancies both in the ordered phases and twin interfaces promotes the recombination of irradiation point defects, thereby enhancing the irradiation tolerance of substoichiometric ZrCx. This work provides a fundamental understanding of correlation between the stoichiometry and irradiation damage in zirconium carbide.
期刊介绍:
Vacuum is an international rapid publications journal with a focus on short communication. All papers are peer-reviewed, with the review process for short communication geared towards very fast turnaround times. The journal also published full research papers, thematic issues and selected papers from leading conferences.
A report in Vacuum should represent a major advance in an area that involves a controlled environment at pressures of one atmosphere or below.
The scope of the journal includes:
1. Vacuum; original developments in vacuum pumping and instrumentation, vacuum measurement, vacuum gas dynamics, gas-surface interactions, surface treatment for UHV applications and low outgassing, vacuum melting, sintering, and vacuum metrology. Technology and solutions for large-scale facilities (e.g., particle accelerators and fusion devices). New instrumentation ( e.g., detectors and electron microscopes).
2. Plasma science; advances in PVD, CVD, plasma-assisted CVD, ion sources, deposition processes and analysis.
3. Surface science; surface engineering, surface chemistry, surface analysis, crystal growth, ion-surface interactions and etching, nanometer-scale processing, surface modification.
4. Materials science; novel functional or structural materials. Metals, ceramics, and polymers. Experiments, simulations, and modelling for understanding structure-property relationships. Thin films and coatings. Nanostructures and ion implantation.