Research on Shielding Performance of Dry Storage Cask for Spent Fuels

被引:0
作者
Huang L. [1 ,2 ]
Tang S. [1 ,2 ]
Liu J. [1 ,2 ]
Yang S. [1 ,2 ]
机构
[1] State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, Shenzhen, 518172, Guangdong
[2] China Nuclear Power Design Co. Ltd., Shenzhen, 518026, Guangdong
来源
Hedongli Gongcheng/Nuclear Power Engineering | 2019年 / 40卷 / 03期
关键词
Radiation shielding; Spent fuel dry storage; Storage cask;
D O I
10.13832/j.jnpe.2019.03.0052
中图分类号
学科分类号
摘要
The radiation shielding design of spent fuel storage containers is one of the important factors affecting the radiation safety of spent fuel dry storage facilities. Taking the dry storage container independently researched and developed by China as an example, the paper focuses on the reasonable determination of the shielding performance target, the shielding calculation method, the selection of the calculation hypothesis and the analysis of the calculation results. The calculation analysis shows that the designed spent fuel dry storage container is with good shielding performance and meets the radiation safety requirements. © 2019, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
引用
收藏
页码:52 / 56
页数:4
相关论文
共 2 条
[1]  
Hermann O.W., Westfall R.M., ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms Manual, pp. 33-55, (1998)
[2]  
MCNP-A General Monte Carlo N-Particle Transport Code, pp. 94-100, (1997)