| 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.
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