Nuclear Engineering and Technology

  • 제52권10호
  • /
  • Pages.2387-2393
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  • 2020
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Development of gradient composite shielding material for shielding neutrons and gamma rays

  • Hu, Guang (Xi'an Jiaotong University) ;
  • Shi, Guang (Nuclear Power Institute of China) ;
  • Hu, Huasi (Xi'an Jiaotong University) ;
  • Yang, Quanzhan (State Key Laboratory of Light Alloy Foundry Technology for High-end Equipment Shenyang Research Institute of Foundry Co. Ltd.) ;
  • Yu, Bo (State Key Laboratory of Light Alloy Foundry Technology for High-end Equipment Shenyang Research Institute of Foundry Co. Ltd.) ;
  • Sun, Weiqiang (Xi'an Jiaotong University)
  • 투고 : 2019.06.23
  • 심사 : 2020.03.30
  • 발행 : 2020.10.25
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초록

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 ℃, 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.

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참고문헌

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