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乏燃料贮存罐体中子防护结构研究

Research on Spent Fuel Storage Tanks for Neutron Protection Structure
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摘要 使用含硼聚乙烯作为乏燃料贮存罐体外层屏蔽罐中子屏蔽层材料时,由于其对温度比较敏感,若结构设计不合理,在环境温差大或出现事故致使罐体温度变化大时,会使罐体外含硼聚乙烯屏蔽层变形过大,影响结构稳定性和屏蔽效果,如产生间隙和裂纹等,致使射线经间隙或裂纹中散射到环境中,对周围环境造成严重污染。乏燃料贮存罐体中子防护结构采用在燃料贮存罐外加双层中子屏蔽结构,内层为主屏蔽层预留伸缩缝,以适应温差较大的环境和事故工况,外层为补充防护层,可有效解决伸缩缝处泄漏问题。中子屏蔽层上端为敞口设计,用含硼聚乙烯粉末填充,事故工况下粉末将熔融补充填充,保证屏蔽层高度,避免射线外露。 Boron-containing polyethylene could be selected as the neutron shielding of the spent fuel storage tank outer casing shield tank. Because of it's sensitive to temperature, if the structural design is unreasonable, the deformation of boron-containing polyethylene could be too large for the structure stability and shielding effect when the ambient temperature difference is large or the tank temperature changes greatly for accident. This may produce gaps and cracks, who scatter the ray to environment and cause pollution. Double layer structure is used for neutron shielding out of the spent fuel storage tank. The inner layer is the main shielding layer, for which expansion joints are reserved to meet large temperature difference of environment and the accident conditions. The outer layer is a supplementary protective layer, which can effectively solve the problem of leakage at the expansion joints. The top of the shielding structure is designed open, filled with boron-containing polyethylene powder. In accident conditions, the powder will melt to fill, and the height of shielding structure could be kept to avoid radiation exposure.
出处 《核动力工程》 EI CAS CSCD 北大核心 2017年第S1期34-36,共3页 Nuclear Power Engineering
关键词 乏燃料 中子防护 屏蔽 含硼聚乙烯 Spent fuel Neutron Protection Shielding Boron-containing polyethylene
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  • 1郭海萍,安力,牟云峰,王新华,陈渊.D-T中子照射下含硼聚乙烯球泄漏γ能谱测量[J].原子能科学技术,2005,39(3):198-201. 被引量:1
  • 2郭洪生,彭太平,何锡钧,陈法新,冯春.含硼轻材料屏蔽14.1 MeV中子的实验研究[J].原子能科学技术,2005,39(5):474-476. 被引量:2
  • 3赵新辉,谷德山,任万彬,刘林茂.基于MCNP程序模拟的14 MeV中子准直屏蔽材料的研究[J].东北师大学报(自然科学版),2006,38(4):59-63. 被引量:16
  • 4罗征,周新贵,等.核屏蔽材料研究与进展[C].第十二届反应堆数值计算与粒子输运学术会议论文集.合肥:中国核学会,2008:305-311.
  • 5清华大学核能与新能源技术研究院.HTR-10最终安全分析报告[R].北京:清华大学核能与新能源技术研究院,2000.
  • 6LIU J G, XIAO H L, LI C P. Design and full scale test of the fuel handling system[J]. Nuclear Engineering and Design, 2002, 218 : 169-178.
  • 7Dianoux A J, Lander G. Neutron data booklet[Z]. Institut Laue-Langevin, France, 2003.
  • 8Maruyama T, Bouts CJ. Attenuation of 15 MeV neutrons in multilayer shields composed of steel, polyethlene and borated materials[J]. Phys Med Biol, 1972,17(3) : 420-424.
  • 9李德平,潘自强.辐射防护手册第一部分:辐射源与屏蔽[M].北京:原子能出版社,1987.
  • 10Ferrari A, Sala P R, Fasso A, et al. FLUKA: a multi-particle transport code[CP]. CERN-2005-010, 2008, INFN TC_05/ll, SLAC-R 773.

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