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    • 1. 发明授权
    • Method for increasing boron.sup.10 contents of neutron absorbing articles
    • 增加中子吸收制品硼含量的方法
    • US4293598A
    • 1981-10-06
    • US960150
    • 1978-11-13
    • Michael T. HortmanRobert G. Naum
    • Michael T. HortmanRobert G. Naum
    • C08K3/38G21C19/40G21F1/10
    • G21F1/103C08K3/38Y10S376/905Y10T428/31942
    • A method for increasing the boron.sup.10 content of a neutron absorbing article, such as one in flat, flexible sheet shape, includes coating a surface of such article with a solidifiable liquid synthetic organic polymeric material, such as a phenol formaldehyde type resin, applying boron carbide particles to the polymeric material and solidifying the polymer, such as by curing to cross-linked permanently set form, so as to hold the neutron absorbing boron carbide particles in place thereon. In highly preferred embodiments of the invention the boron carbide particles applied will extend beyond the surface of the external material and will serve as anchoring means for applications of subsequent coatings and the plurality of coatings, usually after initial partial curing to solidify them and make them form-retaining, will be permanently cross-linked simultaneously. In another aspect of the invention the plurality of flat neutron absorbing articles may be joined together by contacting surfaces thereof with such a coating material, preferably containing boron carbide particles, and curing it.
    • 用于提高中子吸收制品(例如平板,柔性片状)中的硼10含量的方法包括用可凝固的液体合成有机聚合物材料如酚醛树脂涂覆这种制品的表面,施加碳化硼 颗粒到聚合物材料并固化聚合物,例如通过固化成交联的永久固化形式,以便将中子吸收碳化硼颗粒保持在其上。 在本发明的非常优选的实施方案中,施加的碳化硼颗粒将延伸超出外部材料的表面,并且将用作后续涂层和多个涂层的应用的锚固装置,通常在初始部分固化之后,使它们形成 将会同时永久地交互。 在本发明的另一方面,多个平的中子吸收制品可以通过使其表面与这样的涂层材料接合,优选地包含碳化硼颗粒并固化。
    • 2. 发明授权
    • Neutron absorbing article and method for manufacture of such article
    • 中子吸收制品及其制造方法
    • US4225467A
    • 1980-09-30
    • US854966
    • 1977-11-25
    • Carl H. McMurtryRobert G. NaumDean P. OwensMichael T. Hortman
    • Carl H. McMurtryRobert G. NaumDean P. OwensMichael T. Hortman
    • G21C19/40G21F1/10G21C11/00
    • G21C19/40G21F1/103
    • A neutron absorbing article, preferably in long, thin, flat form, suitable for but not necessarily limited to use in storage racks for spent nuclear fuel at locations between volumes of such stored fuel, to absorb neutrons from said spent fuel and prevent uncontrolled nuclear reaction of the spent fuel material, is composed of finely divided boron carbide particles and a solid, irreversibly cured phenolic polymer, forming a continuous matrix about the boron carbide particles, in such proportions that at least 6% of B.sup.10 from the boron carbide content is present therein. The described articles withstand thermal cycling from repeated spent fuel insertions and removals, withstand radiation from said spent nuclear fuel over long periods of time without losing desirable neutron absorbing and physical properties, are sufficiently chemically inert to water so as to retain neutron absorbing properties if brought into contact with it, are not galvanically corrodible and are sufficiently flexible so as to withstand operational basis earthquake and safe shutdown earthquake seismic events, without loss of neutron absorbing capability and other desirable properties, when installed in storage racks for spent nuclear fuel. The disclosure also relates to a plurality of such neutron absorbing articles in a storage rack for spent nuclear fuel and to a method for the manufacture of the articles.
    • 一种中子吸收制品,优选为长而薄的平坦形式,适用于但不一定限于在这种储存燃料的体积之间的位置处用于废核燃料的储存架中,以从所述乏燃料中吸收中子并防止不受控制的核反应 的乏燃料材料由细碎的碳化硼颗粒和固体的不可逆固化的酚醛聚合物组成,其形成了围绕碳化硼颗粒的连续的基体,其比例使得来自碳化硼含量的B10至少为6% 其中。 所描述的物品耐受重复的乏燃料插入和去除的热循环,在长时间内耐受来自所述废核燃料的辐射,而不失去理想的中子吸收和物理性质,对水充分地具有化学惰性,从而保持中子吸收性能,如果带来 与电极接触时,不会电流腐蚀,并且具有足够的柔性,以便在安装在废核燃料的储存架上时,能够承受操作基础地震和安全停堆地震事件,而不损失中子吸收能力和其他所需性能。 本公开还涉及用于乏核燃料的储存架中的多个这样的中子吸收制品和用于制造制品的方法。
    • 3. 发明授权
    • Method for manufacturing neutron absorbing article
    • US4287145A
    • 1981-09-01
    • US133182
    • 1980-03-24
    • Carl H. McMurtryRobert G. NaumDean P. OwensMichael T. Hortman
    • Carl H. McMurtryRobert G. NaumDean P. OwensMichael T. Hortman
    • G21C19/40G21F1/10B29J5/00
    • G21F1/103G21C19/40
    • A neutron absorbing article, preferably in long, thin, flat form, suitable for but not necessarily limited to use in storage racks for spent nuclear fuel at locations between volumes of such stored fuel to absorb neutrons from said spent fuel and prevent uncontrolled nuclear reaction of the spent fuel material, is composed of finely divided boron carbide particles and a solid, irreversibly cured phenolic polymer forming a continuous matrix about the boron carbide particles, in such proportions that at least 6% of B.sup.10 from the boron carbide content is present therein. The described structures possess a multiplicity of desirable properties for the use mentioned, including withstanding thermal cycling from repeated spent fuel insertions and removals, withstanding radiation from said spent nuclear fuel over long periods of time without losing desirable neutron absorbing and physical properties, being sufficiently chemically inert to water so as to retain neutron absorbing properties if brought into contact with it, not being galvanically corroding and being sufficiently flexible so as to withstand operational basis earthquake and safe shutdown earthquake seismic events without loss of neutron absorbing capability and other desirable properties when installed in storage racks for spent nuclear fuel. In preferred embodiments of the invention the phenolic polymer is a phenol formaldehyde type polymer, such as a trimethylol phenol formaldehyde type polymer, the boron carbide contains at least 12% of B.sup.10, the plate contains from 8.0 to 11.5% thereof, the plate density is 1.6 to 2.1 g./cc. and the proportions of boron carbide (which may be accompanied by limited amounts of certain impurities) and phenol formaldehyde type polymer (preferably free of halogens, mercury, lead and sulfur) are from 20 to 35% of the former and 65 to 80% of the latter. The invention also relates to a plurality of such neutron absorbing articles in a storage rack for spent nuclear fuel and to a method for the manufacture of the articles. In the manufacturing method a portion of the phenol formaldehyde type resin, in liquid state, is mixed with the boron carbide particles, compacted and cured, after which the cured article is impregnated with additional phenol formaldehyde type resin, which is then cured to make the final product.
    • 4. 发明授权
    • Reflector with directional control of visible and infra-red radiation
    • 反射器具有可见光和红外辐射的方向控制
    • US06212004B1
    • 2001-04-03
    • US09410924
    • 1999-10-01
    • Grzegorz StachowiakRobert G. Naum
    • Grzegorz StachowiakRobert G. Naum
    • G02B522
    • H01J61/025F21V7/22F21V9/04G02B5/282H01J61/35
    • A reflector providing directional control of visible and infra-red radiation emanating from a lamp held within the reflector. The reflector includes a first, optical interference coating applied to the interior surface of the dome-shaped portion of the reflector which is operable to transmit infra-red radiation while reflecting visible light. A second coating which is non-transmissive to IR radiation is applied to selected portions of the reflector body, and preferably to the area adjacent the neck portion of the reflector whereby components placed rearwardly of the reflector are protected from IR radiation. Various application techniques are disclosed, and the second coating may be applied in manners allowing for coding of reflectors of different types, as well as creating an aesthetically pleasing effect on surfaces illuminated by the IR radiation transmitted rearwardly of the reflector. Visible light escaping from the neck portion of prior art reflectors is also addressed by the present invention.
    • 反射器提供对从保持在反射器内的灯发出的可见光和红外辐射的方向控制。 反射器包括施加到反射器的圆顶形部分的内表面的第一光学干涉涂层,其可操作以在反射可见光的同时传输红外辐射。 对IR辐射不透光的第二涂层被施加到反射体的选定部分,并且优选地施加到与反射器的颈部相邻的区域,从而将放置在反射器后方的部件保护免受IR辐射。 公开了各种应用技术,并且可以以允许对不同类型的反射器进行编码的方式应用第二涂层,以及对由反射器向后传输的IR辐射照射的表面产生美学上令人愉快的效果。 通过本发明也解决了从现有技术的反射器的颈部逸出的可见光。
    • 5. 发明授权
    • Method for manufacture of neutron absorbing article
    • 中子吸收制品的制造方法
    • US4313973A
    • 1982-02-02
    • US133157
    • 1980-03-24
    • Carl H. McMurtryRobert G. NaumPaul F. Forsyth
    • Carl H. McMurtryRobert G. NaumPaul F. Forsyth
    • B29C70/02B29C70/88D06M11/74D06M15/41G21F1/12B05D1/28B05D5/00B05D5/02
    • B29C70/025B29C70/88D06M11/74D06M15/41G21F1/12
    • A composite, neutron absorbing, coated article, normally flat and thin and of comparatively light weight, suitable for installation in storage racks for spent nuclear fuel and for other neutron absorbing applications, includes a backing member, preferably of flexible material such as woven fiberglass cloth, a synthetic organic polymeric coating or a plurality of such coatings on the backing member, preferably of cured phenolic resin, such as phenol formaldehyde or trimethylolphenol formaldehyde and boron carbide particles held to the backing member by the cured coating or a plurality of such coatings. Also described is a method for the manufacture of the neutron absorbing coated article and the use of such an article. In a preferred method the backing member is first coated on both sides thereof with a filling coating of thermosettable liquid phenolic resin, which is then partially cured to solid state, one side of the backing member is then coated with a mixture of thermosettable liquid resin and finely divided boron carbide particles and the resin is partially cured to solid state, the other side is coated with a similar mixture, larger boron carbide particles are applied to it and the resin is partially cured to solid state, such side of the article is coated with thermosettable liquid phenolic resin, the resin is partially cured to solid state and such resin, including previously applied partially cured resins, is cured to final cross-linked and permanently set form.
    • 通常平坦而薄且重量较轻的复合中子吸收涂层制品适用于安装在废核燃料和其他中子吸收应用的储存架中,包括背衬构件,优选为柔性材料,例如编织玻璃纤维布 ,背衬构件上的合成有机聚合物涂层或多个这样的涂层,优选固化的酚醛树脂,例如苯酚甲醛或三羟甲基酚甲醛,以及通过固化的涂层或多个这样的涂层保持在背衬构件上的碳化硼颗粒。 还描述了制造中子吸收涂层制品的方法和这种制品的用途。 在优选的方法中,首先在其两侧涂覆有背衬构件的可热固的液体酚醛树脂的填充涂层,然后将其部分固化成固体状态,然后用热固性液体树脂和 精细分散的碳化硼颗粒和树脂部分固化成固体状态,另一侧涂覆有类似的混合物,较大的碳化硼颗粒被施加到树脂上并将树脂部分固化成固态,制品的这一面被涂覆 使用可热固的液体酚醛树脂,将树脂部分固化成固态,并将这种树脂(包括预先涂敷的部分固化的树脂)固化成最终交联和永久固定的形式。
    • 6. 发明申请
    • Substrate having one or more grooved surfaces to suppress destructive acoustic interference and a method of making such a substrate
    • 具有一个或多个凹槽表面以抑制破坏性声学干扰的基板和制造这种基板的方法
    • US20080190169A1
    • 2008-08-14
    • US11707183
    • 2007-02-14
    • Robert G. NaumZaegyoo Hah
    • Robert G. NaumZaegyoo Hah
    • G01N29/30
    • G01N29/30A61B8/587
    • An ultrasound test object, i.e., a phantom, for the calibration of the imaging fidelity of acoustical imagining equipment comprises a substrate with a surface that is comprised of grooves having at least one reflecting surface with at least one scattering test target disposed at a desired distance from the reflecting surface. The reflecting surface is at an angle to the direction of propagation of beamed acoustical energy where the angle is predetermined for directionally controlled scattering of pulsed acoustical waves away from the surface thereby suppressing destructive interference between waves not impinging on the substrate and substrate-surface-reflected waves, thus increasing the field magnitude of echoed waves, thereby providing a phantom offering high resolution, complexity, and precision. A method for testing the performance of acoustical testing equipment is also taught. Reflection surfaces may be planar of curved and scatters may be randomly positioned on the reflecting surface as individual scatterers.
    • 用于校准声学想象设备的成像保真度的超声波测试对象(即,体模)包括具有表面的基底,该表面由具有至少一个反射表面的凹槽组成,至少一个反射表面具有设置在所需距离 从反射面。 反射表面与被束缚声能的传播方向成角度,其中角度被预定用于远离表面的脉冲声波的方向受控散射,从而抑制不冲击基板的波和基板表面反射的波浪之间的破坏性干扰 波,从而增加了回波的场强,从而提供了高分辨率,复杂性和精度的幻像。 还教导了一种用于测试声学测试设备性能的方法。 反射表面可以是平面的,并且散射可以作为单独的散射体被随机地放置在反射表面上。
    • 7. 发明授权
    • Neutron absorbing article and method for manufacture thereof
    • 中子吸收制品及其制造方法
    • US4218622A
    • 1980-08-19
    • US870237
    • 1978-01-17
    • Carl H. McMurtryRobert G. NaumPaul F. Forsyth
    • Carl H. McMurtryRobert G. NaumPaul F. Forsyth
    • B29C70/02B29C70/88G21F1/12G21C11/00
    • B29C70/88B29C70/025G21F1/12
    • A composite, neutron absorbing, coated article, suitable for installation in storage racks for spent nuclear fuel and for other neutron absorbing applications, includes a backing member, preferably of flexible material such as woven fiberglass cloth, a synthetic organic polymeric coating or a plurality of such coatings on the backing member, preferably of cured phenolic resin, such as phenol formaldehyde or trimethylolphenol formaldehyde and boron carbide particles held to the backing member by the cured coating or a plurality of such coatings. Also within the invention is a method for the manufacture of the neutron absorbing coated article and the use of such an article. In a preferred method the backing member is first coated on both sides thereof with a filling coating of thermosettable liquid phenolic resin, which is then partially cured to solid state, one side of the backing member is then coated with a mixture of thermosettable liquid resin and finely divided boron carbide particles and the resin is partially cured to solid state, the other side is coated with a similar mixture, larger boron carbide particles are applied to it and the resin is partially cured to solid state, such side of the article is coated with thermosettable liquid phenolic resin, the resin is partially cured to solid state and such resin, including previously applied partially cured resins, is cured to final cross-linked and permanently set form.
    • 适用于安装在废核燃料和其他中子吸收应用的存储架中的复合中子吸收涂层制品包括背衬构件,优选为柔性材料,例如编织玻璃纤维布,合成有机聚合物涂层或多个 背衬构件上的这种涂层,优选固化的酚醛树脂,例如苯酚甲醛或三羟甲基酚甲醛,以及通过固化的涂层或多个这样的涂层保持在背衬构件上的碳化硼颗粒。 本发明还有一种制造中子吸收涂层制品的方法和这种制品的用途。 在优选的方法中,首先在其两侧涂覆有背衬构件的可热固的液体酚醛树脂的填充涂层,然后将其部分固化成固体状态,然后用热固性液体树脂和 精细分散的碳化硼颗粒和树脂部分固化成固体状态,另一侧涂覆有类似的混合物,较大的碳化硼颗粒被施加到树脂上并将树脂部分固化成固态,制品的这一面被涂覆 使用可热固的液体酚醛树脂,将树脂部分固化成固态,并将这种树脂(包括预先涂敷的部分固化的树脂)固化成最终交联和永久固定的形式。
    • 8. 发明授权
    • Neutron absorbing article
    • 中子吸收制品
    • US4156147A
    • 1979-05-22
    • US866101
    • 1977-12-30
    • Robert G. NaumDean P. OwensGeorge I. Dooher
    • Robert G. NaumDean P. OwensGeorge I. Dooher
    • G21F1/10G21F1/12G21C11/00
    • G21F1/12G21F1/103
    • 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 binding 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 and 9:1 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.
    • {PG,1 A中子吸收制品,优选为平板形式并适用于废核燃料的储存架,包括碳化硼颗粒,稀释剂颗粒和固化的不可逆固化的酚醛聚合物,固化至连接基体上的硼 碳化物和稀释剂颗粒。 碳化硼和稀释剂颗粒的总含量是制品的主要比例,而固化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和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。