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...

Full description

Bibliographic Details
Main Authors: Guang Hu, Guang Shi, Huasi Hu, Quanzhan Yang, Bo Yu, Weiqiang Sun
Format: Article
Language:English
Published: Elsevier 2020-10-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573319305157
id doaj-7521d7bf7764428a86873ab25efb18ff
record_format Article
spelling 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
work_keys_str_mv AT guanghu developmentofgradientcompositeshieldingmaterialforshieldingneutronsandgammarays
AT guangshi developmentofgradientcompositeshieldingmaterialforshieldingneutronsandgammarays
AT huasihu developmentofgradientcompositeshieldingmaterialforshieldingneutronsandgammarays
AT quanzhanyang developmentofgradientcompositeshieldingmaterialforshieldingneutronsandgammarays
AT boyu developmentofgradientcompositeshieldingmaterialforshieldingneutronsandgammarays
AT weiqiangsun developmentofgradientcompositeshieldingmaterialforshieldingneutronsandgammarays
_version_ 1724616599918346240