{"title":"利用蒙特卡洛模型对 ALFRED 铅冷快堆堆芯进行中子研究","authors":"Saeed Zare Ganjaroodi, Ehsan Zarifi","doi":"10.1007/s10512-024-01054-2","DOIUrl":null,"url":null,"abstract":"<div><p>A Lead-Cooled Fast Reactor (LFR) is one of the six advanced fourth-generation reactors that many countries have been interested in designing, constructing, or develop them in the world. ALFRED reactor design investigated in this paper has 125 (MW) electric power and is being cooled by lead. The main purpose of the ALFRED project is to design and construct a reactor with high safety performance and reliability in all operation modes. In the present study, Monte Carlo codes MCNPX and SuperMC are used to calculate the neutronic parameters of the ALFRED reactor core including effective multiplication factor, kinetic parameters, neutron flux, and power distribution based on the latest design data. According to the results, the insertion of the control rods into the core can move the maximum flux height of about 40% to 50% to the end. Also, comparing codes’ results show an appropriate consistency.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"134 3-4","pages":"264 - 274"},"PeriodicalIF":0.4000,"publicationDate":"2024-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling\",\"authors\":\"Saeed Zare Ganjaroodi, Ehsan Zarifi\",\"doi\":\"10.1007/s10512-024-01054-2\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>A Lead-Cooled Fast Reactor (LFR) is one of the six advanced fourth-generation reactors that many countries have been interested in designing, constructing, or develop them in the world. ALFRED reactor design investigated in this paper has 125 (MW) electric power and is being cooled by lead. The main purpose of the ALFRED project is to design and construct a reactor with high safety performance and reliability in all operation modes. In the present study, Monte Carlo codes MCNPX and SuperMC are used to calculate the neutronic parameters of the ALFRED reactor core including effective multiplication factor, kinetic parameters, neutron flux, and power distribution based on the latest design data. According to the results, the insertion of the control rods into the core can move the maximum flux height of about 40% to 50% to the end. Also, comparing codes’ results show an appropriate consistency.</p></div>\",\"PeriodicalId\":480,\"journal\":{\"name\":\"Atomic Energy\",\"volume\":\"134 3-4\",\"pages\":\"264 - 274\"},\"PeriodicalIF\":0.4000,\"publicationDate\":\"2024-04-09\",\"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/s10512-024-01054-2\",\"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/s10512-024-01054-2","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}
引用次数: 0
摘要
铅冷快堆是世界上六种先进的第四代反应堆之一，许多国家都有兴趣设计、建造或开发这种反应堆。本文研究的 ALFRED 反应堆设计功率为 125 兆瓦，采用铅冷却。ALFRED 项目的主要目的是设计和建造一座在所有运行模式下都具有高安全性能和高可靠性的反应堆。本研究根据最新的设计数据，使用蒙特卡罗代码 MCNPX 和 SuperMC 计算 ALFRED 堆芯的中子参数，包括有效倍增因子、动力学参数、中子通量和功率分布。结果显示，将控制棒插入堆芯可将最大通量高度向末端移动约 40% 至 50%。此外，比较规范的结果也显示出适当的一致性。
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling
A Lead-Cooled Fast Reactor (LFR) is one of the six advanced fourth-generation reactors that many countries have been interested in designing, constructing, or develop them in the world. ALFRED reactor design investigated in this paper has 125 (MW) electric power and is being cooled by lead. The main purpose of the ALFRED project is to design and construct a reactor with high safety performance and reliability in all operation modes. In the present study, Monte Carlo codes MCNPX and SuperMC are used to calculate the neutronic parameters of the ALFRED reactor core including effective multiplication factor, kinetic parameters, neutron flux, and power distribution based on the latest design data. According to the results, the insertion of the control rods into the core can move the maximum flux height of about 40% to 50% to the end. Also, comparing codes’ results show an appropriate consistency.
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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