{"title":"Computer simulation of the processing of uranium mononitride with an argon-oxygen gas mixture","authors":"A.Y. Galashev , Yu.P. Zaikov , O.R. Rakhmanova , Yu.S. Mochalov","doi":"10.1016/j.anucene.2025.111736","DOIUrl":null,"url":null,"abstract":"<div><div>Uranium mononitride (UN) appears to be one of the most efficient fuels for nuclear reactors. The creation of a closed fuel cycle requires the reprocessing of spent nuclear fuel (SNF). The spent fuel reprocessing cycle includes the conversion of nitride fuel into actinide oxides. The oxidation of UN in an oxygen-argon environment at a temperature of 923 K was studied using the molecular dynamics method. A significant difference in the rate of oxide formation for crystalline and amorphous UN particles was revealed. The structure of these particles during the transition from nitride to uranium oxides was studied in detail based on the calculation of partial radial distribution functions and the construction of hybrid polyhedra. For a particle with an amorphous structure, the amount of U–O bonds created significantly exceeds the corresponding characteristic for a crystalline particle. This is facilitated by more intense fragmentation of the amorphous particle in the gaseous Ar–O mixture. Temperature is a more important regulator of the oxidation process than the oxygen concentration in the gas mixture. The destruction of U–N bonds leads to the formation of nitrogen gas, and when U–O bonds are formed, clusters of uranium oxides are created, tending to agglomeration.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111736"},"PeriodicalIF":1.9000,"publicationDate":"2025-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925005535","RegionNum":3,"RegionCategory":"工程技术","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
Uranium mononitride (UN) appears to be one of the most efficient fuels for nuclear reactors. The creation of a closed fuel cycle requires the reprocessing of spent nuclear fuel (SNF). The spent fuel reprocessing cycle includes the conversion of nitride fuel into actinide oxides. The oxidation of UN in an oxygen-argon environment at a temperature of 923 K was studied using the molecular dynamics method. A significant difference in the rate of oxide formation for crystalline and amorphous UN particles was revealed. The structure of these particles during the transition from nitride to uranium oxides was studied in detail based on the calculation of partial radial distribution functions and the construction of hybrid polyhedra. For a particle with an amorphous structure, the amount of U–O bonds created significantly exceeds the corresponding characteristic for a crystalline particle. This is facilitated by more intense fragmentation of the amorphous particle in the gaseous Ar–O mixture. Temperature is a more important regulator of the oxidation process than the oxygen concentration in the gas mixture. The destruction of U–N bonds leads to the formation of nitrogen gas, and when U–O bonds are formed, clusters of uranium oxides are created, tending to agglomeration.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.