{"title":"Shielding design in neutron activation experiment system based on D-T neutron tube","authors":"Jingfei Cai, Shiwei Jing, Dedong He, Yangwenting Ou, Xinyi Ling, Bingbing Li","doi":"10.2298/ntrp2201042c","DOIUrl":null,"url":null,"abstract":"The deuterium-tritium neutron generator should be fully shielded for the safety of the operators participating in the experiments since the D-T neutron generator is commonly used in activation experiments. In this study, MCNP5 code was used to simulate the shielding effect of the neutron thermalization device previously designed by our group with Pb and boron-containing polyethylene as the shielding material. The neutron dose rate outside of the previous thermalization device can not meet the requirement, so a concrete wall is needed between the device and the operators. Two models are designed with concrete walls. One model is that the device and the experimental operators are not in the same room, another one is that the device and the experimental operators are in the same room, and there is an L-shaped concrete wall between them. In both models, the dose rate to the operators was less than 5 ?Svh-1.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":0.9000,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Technology & Radiation Protection","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.2298/ntrp2201042c","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The deuterium-tritium neutron generator should be fully shielded for the safety of the operators participating in the experiments since the D-T neutron generator is commonly used in activation experiments. In this study, MCNP5 code was used to simulate the shielding effect of the neutron thermalization device previously designed by our group with Pb and boron-containing polyethylene as the shielding material. The neutron dose rate outside of the previous thermalization device can not meet the requirement, so a concrete wall is needed between the device and the operators. Two models are designed with concrete walls. One model is that the device and the experimental operators are not in the same room, another one is that the device and the experimental operators are in the same room, and there is an L-shaped concrete wall between them. In both models, the dose rate to the operators was less than 5 ?Svh-1.
期刊介绍:
Nuclear Technology & Radiation Protection is an international scientific journal covering the wide range of disciplines involved in nuclear science and technology as well as in the field of radiation protection. The journal is open for scientific papers, short papers, review articles, and technical papers dealing with nuclear power, research reactors, accelerators, nuclear materials, waste management, radiation measurements, and environmental problems. However, basic reactor physics and design, particle and radiation transport theory, and development of numerical methods and codes will also be important aspects of the editorial policy.