Simulation of neutron shielding performance of concrete material in different incident directions

2nd International Symposium on Application of Materials Science and Energy Materials

材料科学;能源学

Zuo, Yinghong^1 ; Zhu, Jinhui^1 ; Niu, Shengli^1 ; Shang, Peng^1 ; Xie, Honggang^1

Northwest Institute of Nuclear Technology, Xi'an, China^1

关键词: Attenuation effect;    Calculation models;    Cosine of the angles;    Different thickness;    Mono-energetic neutrons;    Monte Carlo simulation methods;    Neutron attenuation;    Transmission coefficients;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/490/2/022014/pdf
DOI  :  10.1088/1757-899X/490/2/022014

学科分类：材料科学（综合）

来源: IOP

【 摘 要 】

The calculation model of isotropic neutron shielding by concrete with different thickness had been established to investigate the neutron shielding performance of concrete in different incident directions. The transmission coefficients of fission neutrons and mono-energetic neutrons at energy of 14 MeV penetrating through the concrete in different directions were calculated by using Monte Carlo simulation method. The results show that the neutron attenuation effects in different incident directions for the same concrete shield at a certain thickness are very different, and the attenuation of concrete to neutrons with perpendicular incident direction is weakest, and the attenuation effect on neutrons with oblique incident direction increases with the increase of the angle between the incident direction and the normal of the concrete shield surface; the tenth-value attenuation thickness in which the intensity of primary neutron will be reduced to 1/10 is approximately proportional to the cosine of the angle between the incident direction and the normal of the shield surface, but also related to the energy of neutron.