基于D-T中子管的中子活化实验系统屏蔽设计

IF 0.9 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI:10.2298/ntrp2201042c
Jingfei Cai, Shiwei Jing, Dedong He, Yangwenting Ou, Xinyi Ling, Bingbing Li
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引用次数: 0

摘要

由于D-T中子发生器常用于活化实验,为了参与实验的操作人员的安全,必须对氘-氚中子发生器进行充分的屏蔽。本研究采用MCNP5代码模拟了本课程组先前设计的以含铅、含硼聚乙烯为屏蔽材料的中子热化装置的屏蔽效果。以前的热化装置外的中子剂量率不能满足要求,因此需要在装置与操作人员之间设置混凝土墙。两个模型设计为混凝土墙。一种是设备和实验操作人员不在同一个房间,另一种是设备和实验操作人员在同一个房间,两者之间有一个l型的混凝土墙。在两种模型中,操作者的剂量率均小于5 ?Svh-1。
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Shielding design in neutron activation experiment system based on D-T neutron tube
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.
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来源期刊
Nuclear Technology & Radiation Protection
Nuclear Technology & Radiation Protection NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.00
自引率
41.70%
发文量
10
审稿时长
6-12 weeks
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.
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