{"title":"浮力诱导的自然对流换热对铅屏蔽放射性物质运输包装热定性的影响","authors":"Sampath Bharadwaj Kota, Seik Mansoor Ali","doi":"10.1016/j.anucene.2025.111570","DOIUrl":null,"url":null,"abstract":"<div><div>Radioactive materials (RM) are stored and transported in well-shielded packages that require certification by the nuclear regulatory authority. Certification is subject to successful demonstration of compliance to a series of tests. Among these, the thermal test is intended to simulate a 30-minute, fully engulfing fire, that may occur during a transport accident involving spillage of large quantities of hydrocarbon fuel. In the present work, the thermal response of a Type-B(U) transport package to fire exposure is investigated by applying CFD techniques. The phase-change processes are captured in detail and the effect of buoyancy-induced natural convection in enhancing the heat transfer and melt fraction is brought out. The duration of convection dominated heat transfer to the package is clearly demarcated from the conduction dominated heat transfer by identifying a cross-over point. The instantaneous heat transfer rates into the package are analysed to bring out the fraction of heat stored as sensible or latent heat. The effect of specifying fire boundary condition using HC-air curve, ISO-834 curve or a constant ambient temperature of 800 °C is also highlighted by means of parametric studies. Finally, some comments on the effect of RM package size on the heat transfer aspects is provided.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"222 ","pages":"Article 111570"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Effect of buoyancy-induced natural convection heat transfer on thermal qualification of lead-shielded radioactive material transport packages\",\"authors\":\"Sampath Bharadwaj Kota, Seik Mansoor Ali\",\"doi\":\"10.1016/j.anucene.2025.111570\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Radioactive materials (RM) are stored and transported in well-shielded packages that require certification by the nuclear regulatory authority. Certification is subject to successful demonstration of compliance to a series of tests. Among these, the thermal test is intended to simulate a 30-minute, fully engulfing fire, that may occur during a transport accident involving spillage of large quantities of hydrocarbon fuel. In the present work, the thermal response of a Type-B(U) transport package to fire exposure is investigated by applying CFD techniques. The phase-change processes are captured in detail and the effect of buoyancy-induced natural convection in enhancing the heat transfer and melt fraction is brought out. The duration of convection dominated heat transfer to the package is clearly demarcated from the conduction dominated heat transfer by identifying a cross-over point. The instantaneous heat transfer rates into the package are analysed to bring out the fraction of heat stored as sensible or latent heat. The effect of specifying fire boundary condition using HC-air curve, ISO-834 curve or a constant ambient temperature of 800 °C is also highlighted by means of parametric studies. Finally, some comments on the effect of RM package size on the heat transfer aspects is provided.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"222 \",\"pages\":\"Article 111570\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-27\",\"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/S0306454925003871\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925003871","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}
Effect of buoyancy-induced natural convection heat transfer on thermal qualification of lead-shielded radioactive material transport packages
Radioactive materials (RM) are stored and transported in well-shielded packages that require certification by the nuclear regulatory authority. Certification is subject to successful demonstration of compliance to a series of tests. Among these, the thermal test is intended to simulate a 30-minute, fully engulfing fire, that may occur during a transport accident involving spillage of large quantities of hydrocarbon fuel. In the present work, the thermal response of a Type-B(U) transport package to fire exposure is investigated by applying CFD techniques. The phase-change processes are captured in detail and the effect of buoyancy-induced natural convection in enhancing the heat transfer and melt fraction is brought out. The duration of convection dominated heat transfer to the package is clearly demarcated from the conduction dominated heat transfer by identifying a cross-over point. The instantaneous heat transfer rates into the package are analysed to bring out the fraction of heat stored as sensible or latent heat. The effect of specifying fire boundary condition using HC-air curve, ISO-834 curve or a constant ambient temperature of 800 °C is also highlighted by means of parametric studies. Finally, some comments on the effect of RM package size on the heat transfer aspects is provided.
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.