{"title":"Determination of Gamma-Ray Shielding Parameters for Concretes and Dosimeters Using MCNPX","authors":"Viswanath P. Singh, H. Tekin","doi":"10.15415/jnp.2020.81009","DOIUrl":null,"url":null,"abstract":"Received: April 16, 2020 Revised: October 19, 2020 Accepted: November 04, 2020 Published Online: December 03, 2020 Gamma-ray shielding parameter for some concretes and dosimeters having large scale applications in radiological protection are presented using MCNPX (version 2.4.0) at different energies. The MCNPX results are compared with experimental, MCNP and XCOM data, and good agreement is being noted. Present study indicates that MCNPX simulation method is suitable and reliable simulation tool to be used as an alternative method for the investigation of gamma-ray interaction. The present geometry can be used as standard geometry for MCNPX simulation for lowas well as high-Z materials.","PeriodicalId":16534,"journal":{"name":"Journal of Nuclear Physics, Material Sciences, Radiation and Applications","volume":"53 1","pages":"73-79"},"PeriodicalIF":0.0000,"publicationDate":"2020-11-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Physics, Material Sciences, Radiation and Applications","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.15415/jnp.2020.81009","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0
Abstract
Received: April 16, 2020 Revised: October 19, 2020 Accepted: November 04, 2020 Published Online: December 03, 2020 Gamma-ray shielding parameter for some concretes and dosimeters having large scale applications in radiological protection are presented using MCNPX (version 2.4.0) at different energies. The MCNPX results are compared with experimental, MCNP and XCOM data, and good agreement is being noted. Present study indicates that MCNPX simulation method is suitable and reliable simulation tool to be used as an alternative method for the investigation of gamma-ray interaction. The present geometry can be used as standard geometry for MCNPX simulation for lowas well as high-Z materials.