SHIELDING MATERIAL AND SHIELDING ELEMENT FOR SHIELDING GAMMA AND NEUTRON RADIATION

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/cm3, - B: 30 to 150 mg/cm3, - H: 15 to 70 mg/cm3. The total density of the shielding material ranges from 3.5 to 5.5 g/cm3. 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.