Compact shielding and irradiator design of a 252Cf neutron source

被引：4

作者：

Nasrabadi, Maryam ^{[1
]}

Ebrahimibasabi, Ehsan ^{[1
]}

Tavakoli-Anbaran, Hossein ^{[1
]}

机构：

[1] Shahrood Univ Technol, Fac Phys & Nucl Engn, Shahrood, Iran

来源：

APPLIED RADIATION AND ISOTOPES | 2019年 / 143卷

关键词：

Neutron source; Moderator; Reflector; Multiplier; Absorber; MCNPX code;

D O I：

10.1016/j.apradiso.2018.10.005

中图分类号：

O61 [无机化学];

学科分类号：

070301 ; 081704 ;

摘要：

New developments are under way to reduce the weight and volume of neutron shielding structures using multi layered materials. The present study aimed at designing and simulating an appropriate neutron shielding material based on a Cf-252 source using MCNPX code. The proposed design is composed of concentric cylinders and sphere layers with a source. The shielding matter consists of paraffin and paraffin + 10% graphite as a moderator, beryllium as a reflector and multiplier and boron carbide and lead tungsten as a thermal neutron and gamma absorber, respectively. The results indicate that, compared to previously reported shielding assemblies, the volume and the weight of the proposed design could be significantly reduced by about 97% and 75%, respectively. Thermal and fast neutron fluxes in the irradiation channel were optimized to achieve maximum values for NAA, PGNAA and other applications.

引用

页码：29 / 34

页数：6

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