Dose evaluation in a portable D-T neutron generator facility by Monte Carlo method

被引：7
|
作者：
Li, Cong [1 ]
Jing, Shiwei [1 ,2 ,3 ]
Xue, Hui [1 ]
机构：
[1] Northeast Normal Univ, Coll Phys, Changchun 130024, Jilin, Peoples R China
[2] China Inst Atom Energy, Beijing 121000, Peoples R China
[3] Sichuan Police Coll, Criminal Sci & Technol Lab, Key Lab Sichuan Higher Educ, Luzhou, Peoples R China
来源：
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2020年 / 324卷 / 02期
关键词：
D-T neutron generator; Monte Carlo method; Dose estimation; Neutron and gamma shielding; DETECTION SYSTEM; SIMULATION; DESIGN; MCNP; EXPLOSIVES; CONCRETE;
D O I：
10.1007/s10967-020-07090-z
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
A portable NG-9 D-T generator can produce fast neutrons with 14 MeV energy in a maximum yield of 4 x 10(8) n/s. Shielding around the neutron emitter is necessary to protect the operators from radiation exposure. MCNP5 was used to evaluate the dose rates in a generic building with an activation room and corresponding six surrounding rooms. Several designs of shielding structure were evaluated to ensure that the total dose rates in surrounding rooms are all less than 5 mu Sv/h. The annual operating time can reach to at least 4081 h around the activation room for the final design.
引用
收藏
页码：533 / 539
页数：7
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