公开(公告)号：EP2225762A2

公开(公告)日：2010-09-08

申请号：EP08872827.4

申请日：2008-12-19

申请人： Commissariat à l'Énergie Atomique et aux Énergies Alternatives ,  Sogefibre

发明人： MARLET Luc ,  PERNELLE, François ,  PETIT-RENAUD, Amel ,  TIQUET, Pascal

IPC分类号： G21F1/04 ,  G21F1/10 ,  G21F1/08 ,  G21F5/12 ,  G21F5/005

CPC分类号： G21F1/04 ,  G21F1/08 ,  G21F1/10 ,  G21F5/005 ,  G21F5/12 ,  G21Y2002/00 ,  G21Y2004/10

摘要： Device (1) for packaging nuclear waste, comprising a concrete container (3) the internal wall of which delimits a cavity in which a metal vessel (2) is housed, the device being characterized in that it further comprises a receptacle (4) made of a thermoplastic polymer of spherolitic structure, placed inside the metal vessel (2) and intended to contain the waste. A device such as this ensures optimal containment while at the same time preserving a structural integrity and a mechanical strength over a period of at least one hundred years, this notably being the case in spite of the presence of chemically aggressive species. The invention also relates to a method of packaging nuclear waste using the device (1).

公开(公告)号：EP1540664A4

公开(公告)日：2009-05-27

申请号：EP03765674

申请日：2003-07-18

申请人： VARIAN MED SYS TECH INC

发明人： BJORKHOLM PAUL

IPC分类号： G01N23/04 ,  G21G1/00 ,  G01T20060101 ,  G01V5/00 ,  G21F1/08 ,  G21K5/00 ,  G21K5/02 ,  H01J35/08 ,  H01J35/16 ,  H05G1/00 ,  H05H9/00

CPC分类号： G01V5/0016 ,  H01J35/16 ,  H01J2235/087

摘要： An X-ray source is disclosed comprising a source of high energy electrons that travel along a longitudinal path. Target material lies along the longitudinal path and X-ray radiation is generated due to impact of the high energy electrons with the target. Shielding material is provided around at least a portion of the target. The shielding material defines a slot extending from the target to an exterior surface of the shielding material, to allow passage of generated radiation. The slot has an axis transverse to the longitudinal path. The axis may be perpendicular longitudinal path. The shielding material may define a plurality of slots having transverse axes. The source of high energy electrons may be a linear accelerator, for example. Scanning systems incorporating such sources are also disclosed. The scanning system comprises a conveying system having a longitudinal axis and the radiation source may be positioned so that the longitudinal path forms an acute angle with respect to the longitudinal axis, to decrease the size of the scanning unit as compared to a unit where the longitudinal axis is perpendicular to the longitudinal path. The longitudinal axis may be parallel to the longitudinal path, to form a more compact scanning system. A plurality of slots may be defined in the shielding material and a corresponding number of conveying systems may be provided to examine a plurality of objects concurrently. Methods of generating radiation and methods of examining objects are also disclosed.

公开(公告)号：EP1119006B1

公开(公告)日：2006-09-20

申请号：EP00949924.5

申请日：2000-07-27

申请人： MITSUBISHI HEAVY INDUSTRIES, LTD.

发明人： Sakaguchi, Yasuhiro, Mitsubishi Heavy Ind. Ltd. ,  Saida, Tomikane, Mitsubishi Heavy Ind. Ltd ,  Murakami, Kazuo, Mitsubishi Heavy Ind. Ltd. ,  Shibue, Kazuhisa, Sumitomo Light Metal Ind. Ltd. ,  Tokizane, Naoki, Sumitomo Light Metal Ind. Ltd. ,  Takahashi, Tatsumi, Sumitomo Light Metal Ind. Ltd

IPC分类号： G21F5/00 ,  G21F1/08 ,  B22F1/00 ,  B22F3/10 ,  C22C21/00 ,  C22C32/00

CPC分类号： G21F1/08 ,  B22F2998/10 ,  B22F2999/00 ,  C22C21/00 ,  C22C32/0057 ,  C22C32/0073 ,  G21Y2002/10 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/40 ,  B22F9/082 ,  B22F3/1208 ,  B22F3/14 ,  B22F3/15 ,  B22F3/20

摘要： An aluminum composite material having the ability to absorb neutrons, characterized in that it comprises an Al or Al alloy base phase and, incorporated therein, a powder of B or a B compound having the ability to absorb neutrons in an amount of 1.5 to 9 wt % in terms of B, and it is prepared through pressure sintering. The above aluminum composite material having the ability to absorb neutrons contains an increased amount of B as compared to a conventional aluminum composite material and thus has improved ability to absorb neutrons, and also is superior in mechanical properties and workability to a conventional aluminum composite material.

公开(公告)号：EP1119006A4

公开(公告)日：2004-11-10

申请号：EP00949924

申请日：2000-07-27

申请人： MITSUBISHI HEAVY IND LTD

发明人： SAKAGUCHI YASUHIRO ,  SAIDA TOMIKANE ,  MURAKAMI KAZUO ,  SHIBUE KAZUHISA ,  TOKIZANE NAOKI ,  TAKAHASHI TATSUMI

IPC分类号： C22C21/00 ,  C22C32/00 ,  G21F1/08 ,  G21F5/00 ,  B22F1/00 ,  B22F3/10

CPC分类号： G21F1/08 ,  B22F2998/10 ,  B22F2999/00 ,  C22C21/00 ,  C22C32/0057 ,  C22C32/0073 ,  G21Y2002/10 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/40 ,  B22F9/082 ,  B22F3/1208 ,  B22F3/14 ,  B22F3/15 ,  B22F3/20

摘要： An aluminum composite material having the ability to absorb neutrons, characterized in that it comprises an Al or Al alloy base phase and, incorporated therein, a powder of B or a B compound having the ability to absorb neutrons in an amount of 1.5 to 9 wt % in terms of B, and it is prepared through pressure sintering. The above aluminum composite material having the ability to absorb neutrons contains an increased amount of B as compared to a conventional aluminum composite material and thus has improved ability to absorb neutrons, and also is superior in mechanical properties and workability to a conventional aluminum composite material.

摘要翻译： 本发明提供具有中子吸收能力的铝复合材料，其通过增加B的含量而提高吸收中子的能力，同时在机械性能和可加工性方面也优于现有技术的材料。 具有中子吸收能力的铝复合材料包含Al或Al合金基体相B或具有中子吸收能力的B化合物，其量使得B的比例为1.5重量％以上至9重量％以下， 并且铝复合材料已经被加压烧结。

公开(公告)号：EP0844312A4

公开(公告)日：1998-12-23

申请号：EP96926611

申请日：1996-08-08

申请人： SUMITOMO METAL IND

发明人： KAJIMURA HARUHIKO

IPC分类号： C22C38/32 ,  C22C38/54 ,  G21F1/08 ,  C22C38/00

CPC分类号： C22C38/32 ,  C22C38/54 ,  G21F1/08 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/101

摘要： A ferritic stainless steel containing the following principal chemical ingredients on the weight percentage basis and preferably satisfying the B-Gd relationship represented by the following formula (1): C: less than 0.01 %, Mn: 1 % or less, Ni: 0.7 % or less, Cr: 13-26 %, B: 0.1-1.1 %, Gd: 0.05-1.5 %, Al: 0.002-0.1 %, N: 0.015 % or less. An austenitic stainless steel containing the following principal chemical ingredients on the weight percentage basis and preferably satisfaying the B-Gd relationship represented by the following formula (1): C: 0.02 % or less, Mn: 0.1-0.9 %, Ni: 7-22 %, Cr: 18-26 %, B: 0.05-0.75 %, Gd: 0.11-1.5 %, Al: 0.005-0.1 %, N: 0.030 % or less. These steels are excellent in not only thermal neutron absorption but also hot workability, cold workability, and corrosion resistances, especially HAZ corrosion resistance, and are low in production cost. Further they have good toughness and weldability and are hence quite suitable as the material of nuclear fuel containers and so forth. Nc >/= 0.8 (1) wherein Nc = {(1-0.015 x B %) x B %} + (4.4 x Gd %).

摘要翻译： 本发明的铁素体不锈钢含有以重量％为基准的B和Gd之间的关系优选满足以下等式（1）的以下主要化学元素：<表>本发明的奥氏体系不锈钢 含有以重量％为基准的B和Gd之间的关系优选满足以下等式（1）的以下主要化学元素：上述本发明的不锈钢的热中子吸收能力优异 ，并且在加工性，冷加工性，耐腐蚀性，特别是HAZ的耐腐蚀性方面的加工性优异，制造成本便宜。 此外，由于韧性，焊接性等也是令人满意的，因此它们非常适合用于核燃料桶等的材料：其中$$

公开(公告)号：EP0806046A4

公开(公告)日：1998-04-22

申请号：EP96909467

申请日：1996-01-23

申请人： LOCKHEED IDAHO TECHNOLOGIES CO

发明人： QUAPP WILLIAM J ,  LESSING PAUL A

IPC分类号： G21F1/04 ,  G21F1/06 ,  G21F1/08 ,  G21F1/10 ,  G21F3/00 ,  G21F5/005 ,  G21F3/04 ,  G21C11/00

CPC分类号： G21F1/042 ,  G21F1/047 ,  G21F1/06 ,  G21F1/085 ,  G21F1/106 ,  G21F3/00 ,  G21F5/005 ,  G21Y2002/301 ,  G21Y2002/601 ,  G21Y2004/101 ,  G21Y2004/60

摘要： The present invention is a radiation shielding composition devised to provide shielding for radioactive materials. The invention is a stabilized depleted uranium material having an air and/or water impermeable layer (28) at the surface (26) of a depleted uranium compound (24). The stabilized depleted uranium material is a stable form of at least one depleted uranium compound, which may be used for radiation shielding as a base component, aggregate or additive, in shielding materials such as concrete, ceramic, bituminous materials, metal, composite, polymercements, polymer, glass or water.

摘要翻译： 用作辐射屏蔽的组合物。 盾牌是含有稳定的铀骨料以减少γ射线和中子吸收组分的混凝土产品，铀骨料和中子吸收组分以足够的量存在于混凝土产品中，以提供密度在约4至约15之间的混凝土 克/厘米3，并且其将以预定厚度衰减γ射线并且在确定的时间段内从放射性材料中投射γ射线和中子发射的中子吸收中子。 该组合物优选为用于储存放射γ射线和中子的放射性材料的容器的形式。 混凝土容器优选地包括金属衬垫和/或金属外壳。 所得的辐射屏蔽容器具有结构良好，长时间稳定的潜力，并且如果需要，容易移动。

公开(公告)号：EP0314025A2

公开(公告)日：1989-05-03

申请号：EP88117634.1

申请日：1988-10-22

申请人： WESTINGHOUSE ELECTRIC CORPORATION

发明人： Nair, Balakrishnan Rabhakrishnan ,  Richardson, Raymond Vernon ,  Mello, Raymond Manuel

IPC分类号： G21F5/00 ,  G21F1/08 ,  G21F1/12

CPC分类号： G21F5/10 ,  G21F5/08 ,  G21F5/12

摘要： The improved, lightweight cask assembly generally comprises at least two, cylindrically shaped and concen­trically disposed structural walls (54, 56, 72, 74) formed from a high-strength titanium alloy and a shielding wall (58, 76) disposed within and supported by the titanium structural walls (54, 56, 72, 74). The inner (56, 74) and outer (54, 72) structural walls are bound together by a reinforcing ring (68) and an end plate assembly (15) likewise formed from a titanium alloy. In the preferred embodiment, the two separate shielding walls (58, 76) made of depleted uranium and particles of boron suspended in a silicone matrix are disposed in the spaces between inner (74), intermediate (72, 56) and outer (54) titanium walls, respectively.

摘要翻译： 改进的重量轻的木桶组件通常包括由高强度钛合金形成的至少两个圆柱形和同心设置的结构壁（54,56,72,74）和屏蔽壁（58,76），所述屏蔽壁布置在由 钛结构壁（54,56,72,74）。 内部（56,74）和外部（54,72）结构壁通过同样由钛合金形成的加强环（68）和端板组件（15）结合在一起。 在优选实施例中，由贫铀和悬浮在硅氧烷基体中的硼颗粒制成的两个单独的屏蔽壁（58,76）设置在内部（74），中间（72,56）和外部（54）之间的空间中， 钛墙分别。

公开(公告)号：EP0275746A1

公开(公告)日：1988-07-27

申请号：EP87402840.0

申请日：1987-12-14

申请人： COMMISSARIAT A L'ENERGIE ATOMIQUE

发明人： Dévillard, Jacques

IPC分类号： G21F1/08 ,  B22F1/00 ,  C22C32/00

CPC分类号： C22C32/0057 ,  B22F1/0003 ,  C22C1/05 ,  G21F1/08

摘要： Le matériau est constitué d'un métal ou d'un alliage de ce métal constituant une matrice et d'un élément dispersoïde (4) ou d'un composé dispersoïde combiné à la matrice par une dispersion de l'élément ou du composé à l'intérieur de la matrice. Il comporte les étapes suivantes :
- on conditionne le matériau de la matrice sous forme de particules sphériques d'un diamètre supérieur à 300 microns ;
- on dépose les particules de l'élément ou du composé dispersoïde (4) sur les particules du matériau constituant la matrice,
- on introduit les particules de matériau constituant la matrice revêtues des particules du composé dispersoïde dans un moule (6) présentant une cavité (11) de forme intérieure correspondant à une forme de pièce à obtenir,
- on soumet les particules du matériau constituant la matrice enrobée à un frittage par compression isostatique à chaud.

摘要翻译： 该材料由构成基体的金属或分散质元素（4）的金属或合金构成，或者通过元素或化合物在基体内的分散体与基体结合的分散相化合物。 它包括以下阶段： - 基质的材料以直径大于300微米的球形颗粒的形式调节; - 分散质元素或化合物（4）的颗粒沉积在构成基质的材料的颗粒上， - 将涂有分散质化合物颗粒的构成基体的材料颗粒引入模具（6）中， 其具有对应于要获得的制品形状的内部模腔（11）， - 构成涂覆基体的材料的颗粒通过等压压缩加热进行烧结操作。

公开(公告)号：EP0211779A1

公开(公告)日：1987-02-25

申请号：EP86420187.6

申请日：1986-07-09

申请人： Fonderies Montupet

发明人： Planchamp, Claude

IPC分类号： G21F1/08

CPC分类号： G21F1/08

摘要： L'invention est relative à un absorbeur de radiations nucléaires.
Elle est caractérisée en ce que cet absorbeur est constitué par un allia­ge de gadolinium et d'aluminium.
Elle trouve son application dans tous les problèmes d'absorption de rayonnements qu'ils soient du domaine civil ou militaire tels que par exemple la réalisation de paniers de transport et de stockage de déchets radioactifs, de racks de piscine pour réacteurs nucléaires, de blindages de véhicules militaires et d'abris anti-atomiques, etc...

摘要翻译： 1.一种用于核辐射的吸收器，其特征在于，其由钆与选自纯铝，合金铝和含有分散相的纯或合金铝的铝合金形成。

公开(公告)号：EP0121529B1

公开(公告)日：1986-07-02

申请号：EP83903090.5

申请日：1983-10-04

申请人： Fonderies Montupet

发明人： PLANCHAMP, Claude

IPC分类号： C22C1/02 ,  G21F1/08

CPC分类号： C22C1/026 ,  G21F1/08

摘要： Method for producing composite alloys based on aluminium which is alloyed or not and containing up to 30 % by weight of boron. Such method is characterized in that the boron is introduced in the liquid aluminium in the form of aluminium boride having the formula AlB2 or AlB12. It finds application in the production of composite alloys resisting to abrasion or intended to be used as neutronic barriers in aqueous or air media.