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1. 发明授权

US4293598A Method for increasing boron.sup.10 contents of neutron absorbing articles 失效
标题翻译：增加中子吸收制品硼含量的方法
公开(公告)号：US4293598A
公开(公告)日：1981-10-06
申请号：US960150
申请日：1978-11-13
申请人： Michael T. Hortman , Robert G. Naum
发明人： Michael T. Hortman , Robert G. Naum
IPC分类号： C08K3/38 , G21C19/40 , G21F1/10
CPC分类号： G21F1/103 , C08K3/38 , Y10S376/905 , Y10T428/31942
摘要： 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.
摘要翻译：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

US4225467A Neutron absorbing article and method for manufacture of such article 失效
标题翻译：中子吸收制品及其制造方法
公开(公告)号：US4225467A
公开(公告)日：1980-09-30
申请号：US854966
申请日：1977-11-25
申请人： Carl H. McMurtry , Robert G. Naum , Dean P. Owens , Michael T. Hortman
发明人： Carl H. McMurtry , Robert G. Naum , Dean P. Owens , Michael T. Hortman
IPC分类号： G21C19/40 , G21F1/10 , G21C11/00
CPC分类号： G21C19/40 , G21F1/103
摘要： 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.
摘要翻译：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

US4287145A Method for manufacturing neutron absorbing article 失效
公开(公告)号：US4287145A
公开(公告)日：1981-09-01
申请号：US133182
申请日：1980-03-24
申请人： Carl H. McMurtry , Robert G. Naum , Dean P. Owens , Michael T. Hortman
发明人： Carl H. McMurtry , Robert G. Naum , Dean P. Owens , Michael T. Hortman
IPC分类号： G21C19/40 , G21F1/10 , B29J5/00
CPC分类号： G21F1/103 , G21C19/40
摘要： 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.

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