Radiation shielding material with heat-transferring property
    52.
    发明公开
    Radiation shielding material with heat-transferring property 失效
    Strahlenabschirmmaterial mitWärmeleiteigenschaften。

    公开(公告)号:EP0405050A2

    公开(公告)日:1991-01-02

    申请号:EP90101319.3

    申请日:1990-01-23

    IPC分类号: G21F3/00

    CPC分类号: G21F5/10 G21F1/12 G21F3/00

    摘要: This invention relates to a shielding material used as a radiation shield of a container containing radioactive wastes. A radiation shield with an excellent heat-transferring property is fabricated from composite particles (A) obtained by coating core particles (a) of radiation-shielding property with a metal (b) of high thermal conductivity. Composite particles are formed into a certain shape of radiation shield by hot-press forming or other forming or packed into the internal space of radioactive waste container or the shield container cavity to compose a radiation shield.

    摘要翻译: 本发明涉及一种用作包含放射性废物的容器的辐射屏蔽的屏蔽材料。 由具有高导热性的金属(b)涂覆辐射屏蔽性的芯颗粒(a)得到的复合颗粒(A)制造具有优良传热特性的辐射屏蔽。 复合颗粒通过热压成型或其他成型或放入放射性废物容器或屏蔽容器腔的内部空间中形成一定形状的辐射屏蔽,以形成辐射屏蔽。

    Neutron absorbing article
    53.
    发明公开
    Neutron absorbing article 失效
    Neutronenabsorbierendes元素。

    公开(公告)号:EP0002714A1

    公开(公告)日:1979-07-11

    申请号:EP78101638.1

    申请日:1978-12-11

    IPC分类号: G21F1/10 G21F1/12 C08L61/06

    CPC分类号: G21F1/12 G21F1/103

    摘要: A neutron absorbing article, preferably in flat plate form and suitable for use in a storage rack for spent nuclear fuel, includes boron carbide particles, diluent particles and a solid, irreversibly cured phenolic polymer cured to a continuous matrix about the boron carbide and diluent particles. The total content of boron carbide and diluent particles is a major proportion of the article and the content of cured phenolic polymer present is a minor proportion. By regulation of the ratio of boron carbide particles to diluent particles, normally within the range of 1:9 to 9:1 1 and preferably within the range of 1:5 to 5:1, the neutron absorbing activity of the product may be controlled, which facilitates the manufacture of articles of particular absorbing activities best suitable for specific applications.

    摘要翻译: 优选为平板形式并适合用于废核燃料的储存架的中子吸收制品包括碳化硼颗粒,稀释剂颗粒和固化到围绕碳化硼和稀释剂颗粒的连续基质的固体不可逆固化的酚醛聚合物 。 碳化硼和稀释剂颗粒的总含量是制品的主要比例,而固化的酚醛聚合物的含量是一小部分。 通过调节碳化硼颗粒与稀释剂颗粒的比率,通常在1:9至9:1的范围内,优选在1:5至5:1的范围内,可以控制产物的中子吸收活性, 这有助于制造最适合于特定应用的特定吸收活性物品。

    Multifunctional chambered radiation shields and systems and related methods
    58.
    发明公开
    Multifunctional chambered radiation shields and systems and related methods 审中-公开
    多功能腔辐射屏蔽和系统及相关方法

    公开(公告)号:EP2517960A3

    公开(公告)日:2017-07-05

    申请号:EP12162174.2

    申请日:2012-03-29

    申请人: Orbital ATK, Inc.

    发明人: Long, David S.

    摘要: Radiation shields (20) include an outer composite wall (22), an inner composite wall (24), and an enclosed fuel chamber (28) disposed between the inner and outer composite walls. A fuel may be contained within the enclosed fuel chamber (28). Spacecraft include one or more such radiation shields (20), and may further include a fuel cell (80) and a conduit (50) providing fluid communication between the fuel chamber (28) of the radiation shield (20) and the fuel cell (80). Methods of forming a radiation shield system include forming an enclosed fuel chamber between an outer composite wall and an inner composite wall of a radiation shield, and providing fuel within the enclosed fuel chamber.

    摘要翻译: 防辐射罩(20)包括外复合壁(22),内复合壁(24)和设置在内复合壁和外复合壁之间的封闭燃料室(28)。 燃料可容纳在封闭的燃料室(28)内。 航天器包括一个或多个这种辐射屏蔽件(20),并且还可以包括燃料电池(80)和导管(50),该导管在辐射屏蔽件(20)的燃料室(28)与燃料电池 80)。 形成辐射屏蔽系统的方法包括在外部复合壁与辐射屏蔽的内部复合壁之间形成封闭燃料腔室,并在封闭燃料腔内提供燃料。

    STRAHLENSCHUTZBAUWERK FÜR EINEN TEILCHENBESCHLEUNIGER
    59.
    发明授权
    STRAHLENSCHUTZBAUWERK FÜR EINEN TEILCHENBESCHLEUNIGER 有权
    辐射防护结构某个粒子

    公开(公告)号:EP2301040B1

    公开(公告)日:2013-11-20

    申请号:EP09777199.2

    申请日:2009-07-15

    IPC分类号: G21F1/12 G21F7/00

    摘要: The invention relates to a radiation shielding construction for beam-guiding devices (28) of a particle accelerator and/or irradiation sites on a particle accelerator, comprising: a load-bearing housing (23) having concrete walls as side walls (14, 16), ceilings (18) and/or floors (10), wherein the concrete walls form a first radiation shielding layer, a second radiation shielding layer (20) comprising a loose or compacted filler mass, particularly soil, at the outside of at least some of the concrete walls, wherein the filler mass is pervious to water to a certain degree so that radionuclides could be flushed from the filler mass, wherein the concrete walls and the second radiation shielding layer (20) comprising the loose or compacted filler mass form an at least double-layer radiation shielding arrangement, and a sealing film (24) for the second radiation shielding layer (20), wherein the sealing film (24) surrounds and delimits the second radiation shielding layer (20) comprising the loose or compacted filler mass on the outside of the second radiation shielding layer (20), wherein the loose or compacted filler mass of the second radiation shielding layer (20) is enclosed between the concrete walls and the sealing film (24) in a water-proof manner, thereby immobilizing the filler mass hydro-geologically.