发明公开
EP2355108A1 Shielding material and shielding element for shielding gamma and neutron radiation
有权
Abschirmungsmaterial und Abschirmungselement zur Abschirmung von Gamma- und Neutronenstrahlung
- 专利标题： Shielding material and shielding element for shielding gamma and neutron radiation
- 专利标题（中）： Abschirmungsmaterial und Abschirmungselement zur Abschirmung von Gamma- und Neutronenstrahlung
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申请号： EP10152973.3申请日： 2010-02-08
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公开(公告)号： EP2355108A1公开(公告)日： 2011-08-10
- 发明人: Türck, Harald , Calzada, Elbio , Schillinger, Burkhard , Grünauer, Florian
- 申请人： Technische Universität München
- 申请人地址： Arcisstrasse 21 80333 München DE
- 专利权人： Technische Universität München
- 当前专利权人： Technische Universität München
- 当前专利权人地址： Arcisstrasse 21 80333 München DE
- 代理机构： Herrmann, Franz
- 主分类号： G21F1/10
- IPC分类号： G21F1/10
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.
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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