{"title":"Kinetics and mechanism of oxidation of simulated spent nuclear fuel segment at 500°C","authors":"Yandong Sun, Zheng Wei, Ying Chen, Fang Liu, Taihong Yan, Tianchi Li, Zhongwei Yuan, Weifang Zheng","doi":"10.1016/j.jnucmat.2024.155581","DOIUrl":null,"url":null,"abstract":"<div><div>The simulated spent nuclear fuel segment were oxidized at 500 °C, which is very important to the voloxidation. The results demonstrate that the average of oxidation rate is 0.395 cm/hr. Besides, the oxide layer formed between the pellet and the hull caused that oxidation carried out along the axial direction of the segment, and the oxidation of the segment meet the crack-spallation model. Finally, by measuring the oxidation rates at different oxygen volume fractions, it was confirmed that the simulated spent fuel segments oxidation macroscopically manifests as a first-order reaction. In addition, the rate-limiting step mainly affected by oxygen concentration.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"605 ","pages":"Article 155581"},"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/S0022311524006822","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
The simulated spent nuclear fuel segment were oxidized at 500 °C, which is very important to the voloxidation. The results demonstrate that the average of oxidation rate is 0.395 cm/hr. Besides, the oxide layer formed between the pellet and the hull caused that oxidation carried out along the axial direction of the segment, and the oxidation of the segment meet the crack-spallation model. Finally, by measuring the oxidation rates at different oxygen volume fractions, it was confirmed that the simulated spent fuel segments oxidation macroscopically manifests as a first-order reaction. In addition, the rate-limiting step mainly affected by oxygen concentration.
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.
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