{"title":"核反应堆生物屏蔽用碳化硼添加剂提高沸石和方铅矿的中子屏蔽能力","authors":"R. Mehrnejad","doi":"10.4172/2161-0398.1000278","DOIUrl":null,"url":null,"abstract":"Biological shielding of nuclear reactor is an important interest and diminishing the intricacy and cost of theseinstallations is important interest. In this paper, we used Datolite and Galena minerals and boron carbide for nuclear reactor shielding aim. Datolite and Galena minerals that exist in many parts of world were used in the concrete mix design. Boron carbide is an important material for neutron absorption processes. The cross section in matter and neutron capture is utilizable causes to explain neutron shielding characteristics of samples. Neutron cross section simulations of samples have done by using a source of 14.1 MeV reactor neutrons. Cross section and number of captured neutrons of each sample were estimated by using Geant4 Monte Carlo code. As a result, growing boron carbide concentration can raise cross section value of Datolite and galena.","PeriodicalId":94103,"journal":{"name":"Journal of physical chemistry & biophysics","volume":"34 1","pages":"1-4"},"PeriodicalIF":0.0000,"publicationDate":"2019-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"Improving Neutron Shielding Capacities of Datolite and Galena by Boron Carbide Additive for Nuclear Reactor Biological Shielding\",\"authors\":\"R. Mehrnejad\",\"doi\":\"10.4172/2161-0398.1000278\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Biological shielding of nuclear reactor is an important interest and diminishing the intricacy and cost of theseinstallations is important interest. In this paper, we used Datolite and Galena minerals and boron carbide for nuclear reactor shielding aim. Datolite and Galena minerals that exist in many parts of world were used in the concrete mix design. Boron carbide is an important material for neutron absorption processes. The cross section in matter and neutron capture is utilizable causes to explain neutron shielding characteristics of samples. Neutron cross section simulations of samples have done by using a source of 14.1 MeV reactor neutrons. Cross section and number of captured neutrons of each sample were estimated by using Geant4 Monte Carlo code. As a result, growing boron carbide concentration can raise cross section value of Datolite and galena.\",\"PeriodicalId\":94103,\"journal\":{\"name\":\"Journal of physical chemistry & biophysics\",\"volume\":\"34 1\",\"pages\":\"1-4\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2019-01-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of physical chemistry & biophysics\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.4172/2161-0398.1000278\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of physical chemistry & biophysics","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.4172/2161-0398.1000278","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Improving Neutron Shielding Capacities of Datolite and Galena by Boron Carbide Additive for Nuclear Reactor Biological Shielding
Biological shielding of nuclear reactor is an important interest and diminishing the intricacy and cost of theseinstallations is important interest. In this paper, we used Datolite and Galena minerals and boron carbide for nuclear reactor shielding aim. Datolite and Galena minerals that exist in many parts of world were used in the concrete mix design. Boron carbide is an important material for neutron absorption processes. The cross section in matter and neutron capture is utilizable causes to explain neutron shielding characteristics of samples. Neutron cross section simulations of samples have done by using a source of 14.1 MeV reactor neutrons. Cross section and number of captured neutrons of each sample were estimated by using Geant4 Monte Carlo code. As a result, growing boron carbide concentration can raise cross section value of Datolite and galena.