贫化铀用于核动力堆防护的屏蔽性能与放射性毒性计算分析

针对贫化铀的γ射线屏蔽进行了实验与模拟计算验证。构建了核动力压水堆屏蔽模型，模拟输出的屏蔽层内中子能谱与实际能谱分布较为一致。采用蒙特卡罗程序与燃耗计算程序相耦合的方法，模拟计算了贫化铀在不同位置处中子、γ混合辐射场中的综合屏蔽性能，并与铅作为屏蔽材料进行了对比分析。模拟计算了屏蔽层中子辐照贫化铀40 a后的活化和裂变产物，分析了材料辐照前后年摄入量限值（ALI）定义下的放射性毒性，结果表明，新增二次产物对放射性毒性影响不大。 

Calculation and Analysis of Shielding Effectiveness and Radio-Toxicity of Depleted Uranium Applied to Nuclear Power Reactor Protection

In this paper, the gamma ray shielding of depleted uranium is verified by experiment and simulation. A nuclear power pressurized water reactor shielding model is constructed, and the simulation distribution of neutron energy spectrum in the shielding layer was consistent with that in practice. The comprehensive shielding performance of depleted uranium in different positions of neutron and gamma mixed radiation field were simulated by the Monte Carlo simulation method and the fuel consumption calculation program, and compared with that of the lead shielding material. The activation and fission products of the depleted uranium irradiated by the shielding neutrons for 40a was simulated and calculated, and the radio-toxicity defined by Annual Limit of Intake (ALI) before and after irradiation of the material was analyzed. The results show that the addition of secondary products has little effect on the radio-toxicity.