{"title":"利用 240Pu 自发裂变源开发测量延迟中子有效部分的方法","authors":"V. A. Grabezhnoy, V. A. Dulin, G. M. Mikhailov","doi":"10.1007/s10512-024-01137-0","DOIUrl":null,"url":null,"abstract":"<div><p>The article presents the results of determining the effective fraction of delayed neutrons β<sub>eff</sub> for a BFS critical assembly whose fuel is composed of metallic plutonium and depleted uranium nitride and dioxide. The traditional method for determining β<sub>eff</sub> by introducing the <sup>252</sup>Cf source into the core is supplemented by the <sup>240</sup>Pu source of spontaneous fissions in the fuel composition. The described modification simplifies the analysis, increases the reliability of results, and can be used in power reactors with plutonium of known composition in which it is impossible to use a <sup>252</sup>Cf source.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"96 - 99"},"PeriodicalIF":0.4000,"publicationDate":"2024-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source\",\"authors\":\"V. A. Grabezhnoy, V. A. Dulin, G. M. Mikhailov\",\"doi\":\"10.1007/s10512-024-01137-0\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>The article presents the results of determining the effective fraction of delayed neutrons β<sub>eff</sub> for a BFS critical assembly whose fuel is composed of metallic plutonium and depleted uranium nitride and dioxide. The traditional method for determining β<sub>eff</sub> by introducing the <sup>252</sup>Cf source into the core is supplemented by the <sup>240</sup>Pu source of spontaneous fissions in the fuel composition. The described modification simplifies the analysis, increases the reliability of results, and can be used in power reactors with plutonium of known composition in which it is impossible to use a <sup>252</sup>Cf source.</p></div>\",\"PeriodicalId\":480,\"journal\":{\"name\":\"Atomic Energy\",\"volume\":\"136 1-2\",\"pages\":\"96 - 99\"},\"PeriodicalIF\":0.4000,\"publicationDate\":\"2024-10-11\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Atomic Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://link.springer.com/article/10.1007/s10512-024-01137-0\",\"RegionNum\":4,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Atomic Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10512-024-01137-0","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source
The article presents the results of determining the effective fraction of delayed neutrons βeff for a BFS critical assembly whose fuel is composed of metallic plutonium and depleted uranium nitride and dioxide. The traditional method for determining βeff by introducing the 252Cf source into the core is supplemented by the 240Pu source of spontaneous fissions in the fuel composition. The described modification simplifies the analysis, increases the reliability of results, and can be used in power reactors with plutonium of known composition in which it is impossible to use a 252Cf source.
期刊介绍：
Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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