{"title":"Verification of the MCNP model of Manganese Bath","authors":"J. Rataj, T. Bily, O. Huml, O. Novak, Pavel Suk","doi":"10.1109/EPE51172.2020.9269226","DOIUrl":null,"url":null,"abstract":"The paper describes verification of the MCNP model of manganese bath used at the Czech Technical University for education purposes. The bath consists of a spherical tank made of plexiglass filled with an aqueous solution of MnSO4with the total volume of 163.3 litres. Neutron sources are introduced into the centre of the bath manually using a dry plexiglass channel. The MCNP model contains all important geometric and material details of the bath including optional neutron source. Its verification was performed based on experimentally determined activity; as well, neutron emission rates for used radionuclide sources were compared. The experiments were performed with two various radionuclide neutron sources (Am-Be and 252Cf). Comparison of calculation results with ENDF/B-VII.1 and JEFF-3.2 nuclear data libraries was performed.","PeriodicalId":177031,"journal":{"name":"2020 21st International Scientific Conference on Electric Power Engineering (EPE)","volume":"1 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2020-10-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"2020 21st International Scientific Conference on Electric Power Engineering (EPE)","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/EPE51172.2020.9269226","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 2
Abstract
The paper describes verification of the MCNP model of manganese bath used at the Czech Technical University for education purposes. The bath consists of a spherical tank made of plexiglass filled with an aqueous solution of MnSO4with the total volume of 163.3 litres. Neutron sources are introduced into the centre of the bath manually using a dry plexiglass channel. The MCNP model contains all important geometric and material details of the bath including optional neutron source. Its verification was performed based on experimentally determined activity; as well, neutron emission rates for used radionuclide sources were compared. The experiments were performed with two various radionuclide neutron sources (Am-Be and 252Cf). Comparison of calculation results with ENDF/B-VII.1 and JEFF-3.2 nuclear data libraries was performed.
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