Development of gradient composite shielding material for shielding neutrons and gamma rays
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...
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doaj-7521d7bf7764428a86873ab25efb18ff2020-11-25T03:20:48ZengElsevierNuclear Engineering and Technology1738-57332020-10-01521023872393Development of gradient composite shielding material for shielding neutrons and gamma raysGuang Hu0Guang Shi1Huasi Hu2Quanzhan Yang3Bo Yu4Weiqiang Sun5Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, ChinaNuclear Power Institute of China, Chengdu, Si Chuan, 610213, ChinaXi'an Jiaotong University, Xi'an, Shaanxi, 710049, China; Corresponding author.State Key Laboratory of Light Alloy Foundry Technology for High-end Equipment Shenyang Research Institute of Foundry Co. Ltd., Shenyang, Liaoning, 110022, ChinaState Key Laboratory of Light Alloy Foundry Technology for High-end Equipment Shenyang Research Institute of Foundry Co. Ltd., Shenyang, Liaoning, 110022, China; Corresponding author.Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, ChinaIn 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.http://www.sciencedirect.com/science/article/pii/S1738573319305157Gradient shielding materialResin matrixNeutron and γ-raysGradient material designMaterial manufacture |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Guang Hu Guang Shi Huasi Hu Quanzhan Yang Bo Yu Weiqiang Sun |
spellingShingle |
Guang Hu Guang Shi Huasi Hu Quanzhan Yang Bo Yu Weiqiang Sun Development of gradient composite shielding material for shielding neutrons and gamma rays Nuclear Engineering and Technology Gradient shielding material Resin matrix Neutron and γ-rays Gradient material design Material manufacture |
author_facet |
Guang Hu Guang Shi Huasi Hu Quanzhan Yang Bo Yu Weiqiang Sun |
author_sort |
Guang Hu |
title |
Development of gradient composite shielding material for shielding neutrons and gamma rays |
title_short |
Development of gradient composite shielding material for shielding neutrons and gamma rays |
title_full |
Development of gradient composite shielding material for shielding neutrons and gamma rays |
title_fullStr |
Development of gradient composite shielding material for shielding neutrons and gamma rays |
title_full_unstemmed |
Development of gradient composite shielding material for shielding neutrons and gamma rays |
title_sort |
development of gradient composite shielding material for shielding neutrons and gamma rays |
publisher |
Elsevier |
series |
Nuclear Engineering and Technology |
issn |
1738-5733 |
publishDate |
2020-10-01 |
description |
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. |
topic |
Gradient shielding material Resin matrix Neutron and γ-rays Gradient material design Material manufacture |
url |
http://www.sciencedirect.com/science/article/pii/S1738573319305157 |
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