Study on the shielding performance of bismuth oxide as a spent fuel dry storage container based on Monte Carlo simulation

Guo-Qiang Zeng; Shuang Qi; Peng Cheng; Sheng Lv; Fei Li; Xiao-Bo Wang; Bing-Hai Li; Qing-Ao Qin

Nuclear Engineering and Technology (Aug 2024)

Study on the shielding performance of bismuth oxide as a spent fuel dry storage container based on Monte Carlo simulation

Guo-Qiang Zeng,
Shuang Qi,
Peng Cheng,
Sheng Lv,
Fei Li,
Xiao-Bo Wang,
Bing-Hai Li,
Qing-Ao Qin

Affiliations

Guo-Qiang Zeng: College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China; Applied Nuclear Technology in Geosciences Key Laboratory of Sichuan Province (Chengdu University of Technology), Chengdu, 610000, China
Shuang Qi: College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China
Peng Cheng: College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China
Sheng Lv: College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China
Fei Li: College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China; Applied Nuclear Technology in Geosciences Key Laboratory of Sichuan Province (Chengdu University of Technology), Chengdu, 610000, China; Department of Physics, Universitat Politècnica de Catalunya, Barcelona, 08028, Spain; Corresponding author. College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China.
Xiao-Bo Wang: College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China; Corresponding author.
Bing-Hai Li: Airborne Survey and Remote Sensing Center of Nuclear Industry, Shijiazhuang, 050000, China; Hebei Key Laboratory of Airborne Detection and Remote Sensing Technology, Shijiazhuang, 050000, China
Qing-Ao Qin: College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu, 610000, China

Journal volume & issue: Vol. 56, no. 8
pp. 3307 – 3314

Abstract

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For traditional spent fuel shielding materials, due to physical and chemical defects and cost constraints, they have been unable to meet the needs. Therefore, this paper carries out the first discussion on the application and performance of bismuth in neutron shielding by establishing Monte Carlo simulation on the neutron flux model of shielded spent fuel. Firstly, functional fillers such as bismuth oxide, lead oxide, boron oxide, gadolinium oxide and tungsten oxide are added to the matrices to compare the shielding rates of aluminum alloy matrix and silicone rubber matrix. The shielding rate of silicone rubber mixture is higher than aluminum alloy mixture, reaching more than 56%. The optimal addition proportion of bismuth oxide and lead oxide is 30%, and the neutron radiation protection efficiency reaches 60%. Then, the mass attenuation coefficients of bismuth oxide, lead oxide, boron oxide, gadolinium oxide and tungsten oxide in silicone rubber matrix are simulated with the change of functional fillers proportion and neutron energy. This simulation result shows that the mixture with functional fillers has good shielding performance for low energy neutrons, but poor shielding effect for high energy neutrons. Finally, in order to further evaluate the possibility of replacing lead oxide with bismuth oxide as shielding material, the half-value layers and various properties of bismuth oxide and lead oxide are compared. The results show that the shielding properties of bismuth oxide and lead oxide are basically the same, and the mechanical properties, heat resistance, radiation resistance and environmental protection of bismuth oxide are better than that of lead oxide. Therefore, in the case of neutron source strengths in the range of 0.01–6 MeV and secondary gamma rays produced below 2.5 MeV, bismuth can replace lead in neutron shielding applications.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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