{"title":"平面多层反应堆屏蔽系统中多群移除扩散方程的解析解","authors":"L.W. Szymendera","doi":"10.1016/0369-5816(65)90150-X","DOIUrl":null,"url":null,"abstract":"<div><p>This paper gives the analytical solution of the set of differential equations describing, in the multigroup removal-diffusion approximation of Boltzmann's transport equation, the neutron flux distributions in the multi-layered plane shield of a nuclear reactor. The solution is obtained in closed form of a linear combination of some well-defined auxiliary expression, which can be easily integrated and differentiated.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 5","pages":"Pages 476-489"},"PeriodicalIF":0.0000,"publicationDate":"1965-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90150-X","citationCount":"2","resultStr":"{\"title\":\"An analytical solution of multi-group removal-diffusion equations, in plane multi-layered, reactor shield system\",\"authors\":\"L.W. Szymendera\",\"doi\":\"10.1016/0369-5816(65)90150-X\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>This paper gives the analytical solution of the set of differential equations describing, in the multigroup removal-diffusion approximation of Boltzmann's transport equation, the neutron flux distributions in the multi-layered plane shield of a nuclear reactor. The solution is obtained in closed form of a linear combination of some well-defined auxiliary expression, which can be easily integrated and differentiated.</p></div>\",\"PeriodicalId\":100973,\"journal\":{\"name\":\"Nuclear Structural Engineering\",\"volume\":\"1 5\",\"pages\":\"Pages 476-489\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1965-05-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1016/0369-5816(65)90150-X\",\"citationCount\":\"2\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Structural Engineering\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/036958166590150X\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Structural Engineering","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/036958166590150X","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
An analytical solution of multi-group removal-diffusion equations, in plane multi-layered, reactor shield system
This paper gives the analytical solution of the set of differential equations describing, in the multigroup removal-diffusion approximation of Boltzmann's transport equation, the neutron flux distributions in the multi-layered plane shield of a nuclear reactor. The solution is obtained in closed form of a linear combination of some well-defined auxiliary expression, which can be easily integrated and differentiated.
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