摘要:
Shielding Material and Shielding Element for Shielding Gamma and Neutron Radiation A material for shielding radiation is disclosed, the material comprising: - a neutron moderator (13) based on a hydrocarbon, - a neutron absorber (12) based on B, - a gamma absorber (11) based on Fe,
wherein the neutron absorber (12), the neutron moderator (13), and the gamma absorber (11) form a mixture, which comprises unbound particles and in which Fe, B and H have the following partial densities: - Fe: 2 to 5.5 g/cm 3 , - B: 30 to 150 mg/cm 3 , - H: 15 to 70 mg/cm 3 . The total density of the shielding material ranges from 3.5 to 5.5 g/cm 3 . The shielding material remains in a particulate form and can be reused several times without reprocessing and does not pose a health hazard while delivering maximum shielding performance for sources that generate a combination of particle and gamma radiation.
摘要翻译:用于屏蔽伽马和中子辐射的屏蔽材料和屏蔽元件公开了一种用于屏蔽辐射的材料,该材料包括: - 基于烃的中子减速器(13), - 基于B的中子吸收器(12),γ吸收器 (11)基于Fe,其中中子吸收体(12),中子减速剂(13)和γ吸收体(11)形成混合物,其包含未结合的颗粒,并且其中Fe,B和H具有以下部分密度 :Fe:2〜5.5g / cm 3,-B:30〜150mg / cm 3,-H:15〜70mg / cm 3。 屏蔽材料的总密度为3.5〜5.5g / cm 3。 屏蔽材料保持颗粒形式,并且可以重新使用几次而不需要再处理,并且不产生健康危害,同时为产生颗粒和γ辐射的组合的源提供最大屏蔽性能。