{"title":"铁矿分析仪的蒙特卡罗模拟","authors":"M.T. Rainbow","doi":"10.1016/0020-708X(85)90022-5","DOIUrl":null,"url":null,"abstract":"<div><p>The general purpose Monte Carlo code MORSE and nuclear data derived from ENDF/B-IV are used to model an iron ore analyser which detects thermal neutron capture γ rays from <sup>56</sup>Fe. Measurements on an actual system have been simulated. Calculated detector count rates agree, after normalisation, with measured values to within the accuracy of the calculations (∼5% at 1σ). Practical use of the model is dependent upon improving the efficiency of the calculations.</p></div>","PeriodicalId":22517,"journal":{"name":"The International journal of applied radiation and isotopes","volume":"36 11","pages":"Pages 889-892"},"PeriodicalIF":0.0000,"publicationDate":"1985-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0020-708X(85)90022-5","citationCount":"1","resultStr":"{\"title\":\"Monte Carlo simulation of an iron ore analyser\",\"authors\":\"M.T. Rainbow\",\"doi\":\"10.1016/0020-708X(85)90022-5\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>The general purpose Monte Carlo code MORSE and nuclear data derived from ENDF/B-IV are used to model an iron ore analyser which detects thermal neutron capture γ rays from <sup>56</sup>Fe. Measurements on an actual system have been simulated. Calculated detector count rates agree, after normalisation, with measured values to within the accuracy of the calculations (∼5% at 1σ). Practical use of the model is dependent upon improving the efficiency of the calculations.</p></div>\",\"PeriodicalId\":22517,\"journal\":{\"name\":\"The International journal of applied radiation and isotopes\",\"volume\":\"36 11\",\"pages\":\"Pages 889-892\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1985-11-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1016/0020-708X(85)90022-5\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"The International journal of applied radiation and isotopes\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/0020708X85900225\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"The International journal of applied radiation and isotopes","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0020708X85900225","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
The general purpose Monte Carlo code MORSE and nuclear data derived from ENDF/B-IV are used to model an iron ore analyser which detects thermal neutron capture γ rays from 56Fe. Measurements on an actual system have been simulated. Calculated detector count rates agree, after normalisation, with measured values to within the accuracy of the calculations (∼5% at 1σ). Practical use of the model is dependent upon improving the efficiency of the calculations.
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