基于钨/钆三层结构的中子/γ一体化辐射防护服材料的设计

Design of W/Gd-based Trilaminar Neutron/γ-integrated RadiationProtection Clothing Material

当发生核事故与核应急时,反应堆内的高辐射水平会对应急人员的健康造成极大危害。目前我国的辐射防护产品多为防护单一射线类型,且针对的是低能射线,无法满足核应急作业的需求。本工作基于蒙特卡罗粒子输运程序,设计了一种中子/γ一体化辐射防护材料,对其厚度与屏蔽性能进行了研究,并将蒙特卡罗模拟的屏蔽性能数据与实验测试结果进行了对比验证。结果表明,5 mm的厚度能满足屏蔽性能要求,中能γ射线与慢中子屏蔽率的模拟值分别为21.52%和78.7%,而实验测试值分别为20.61%和88.2%,模拟结果与实验结果符合较好,说明蒙特卡罗方法对辐射防护材料设计具有很好的指导意义。

In the event of nuclear accidents or emergency,high radiation in the reactor will do great harm to human health.Currently,domestic radiation protection products are mostly targeted for the single-type radiation and aimed at low-energy radiation,which can not meet the needs of nuclear emergency operations.In this work,a kind of neutron/γradiation protection material was designed based on the Monte Carlo particle transport program.The thickness and shielding performance were studied,and the shielding performance simulated by Monte Carlo was verified by experimental tests.The results show that thickness of 5 mm can meet the requirements of radiation shielding.The simulated shielding rates of medium energyγ-rays and slow neutrons are 21.42%and 78.79%,while the experimental values are 20.61%and 88.2%respectively.The simulation results are in good agreement with the experimental results,indicating that the Monte Carlo method had good guiding significance for radiation protection material design.