Development of gradient composite shielding material for shielding neutrons and gamma ray

Guang Hu; Guang Shi; Huasi Hu; Quanzhan Yang; Bo Yu; Weiqiang Sun

doi:https://doi.org/10.1016/j.net.2020.03.029

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자료유형: 학술저널

저자정보: Guang Hu (Xi'an Jiaotong University) Guang Shi (Xi'an Jiaotong University) Huasi Hu (Nuclear Power Institute of China) Quanzhan Yang (State Key Laboratory of Light Alloy Foundry Technology for High-end Equipment Shenyang Research Ins) Bo Yu (State Key Laboratory of Light Alloy Foundry Technology for High-end Equipment Shenyang Research Ins) Weiqiang Sun (Xi'an Jiaotong University)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제10호

발행연도: 2020.10

수록면: 2,387 - 2,393 (7page)

DOI: https://doi.org/10.1016/j.net.2020.03.029

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In this study, a gradient material for shielding neutrons and gamma rays was developed, which consists of epoxy resin, boron carbide (B4C), lead (Pb) and a little graphene oxide. It aims light weight and compact, which will be applied on the transportable nuclear reactor. The material is made up of sixteen layers, and the thickness and components of each layer were designed by genetic algorithm (GA) combined with Monte Carlo N Particle Transport (MCNP). In the experiment, the viscosities of the epoxy at different temperatures were tested, and the settlement regularity of Pb particles and B4C particles in the epoxy was simulated by matlab software. The material was manufactured at 25 °C, the Pb C and O elements of which were also tested, and the result was compared with the outcome of the simulation. Finally, the material's shielding performance was simulated by MCNP and compared with the uniformity material's. The result shows that the shielding performance of gradient material is more effective than that of the uniformity material, and the difference is most noticeable when the materials are 30 cm thick.

#Gradient shielding materia #lResin matrix #Neutron and γ-rays #Gradient material design #Material manufacture

참고문헌 (12)

참고문헌 신청

2013 / Legal and Institutional Issues of Transportable Nuclear Power Plants: A Preliminary Study

Liberato Ferrara / 2012 / A magnetic method for non destructive monitoring of fiber dispersion and orientation in steel fiber reinforced cementitious compositesdpart 1 : method calibration / Mater. Struct 45(4):575~589

Huasi Hu / 2008 / Study on composite material for shielding mixed neutron and g erays / IEEE Trans. Nucl. Sci 55(4)

A. El-Sayed Abdo / 2002 / Calculation of the cross-sections for fast neutrons and gamma-rays in concrete shields / Ann. Nucl. Energy 29:1977~1988

Vishwanath P. Singh / 2014 / Gamma ray and neutron shielding properties of some alloy materials / Ann. Nucl. Energy 64:301~310

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