公开(公告)号：WO2005034138A3

公开(公告)日：2005-04-14

申请号：PCT/FR2004/050483

申请日：2004-10-05

Applicant: COMMISSARIAT A L'ENERGIE ATOMIQUE ,  COMPAGNIE GENERALE DES MATIERES NUCLEAIRES ,  DUBOIS, Sylvie ,  Cecilia, Gilles

Inventor： DUBOIS, Sylvie ,  Cecilia, Gilles

IPC: G21C3/62

Abstract: L'invention se rapporte à un procédé de fabrication de pastilles d'un combustible nucléaire à base d'oxyde mixte (U,Pu)O 2 ou (U,Th)O 2 , qui comprend a) la préparation d'un mélange primaire de poudres par co-broyage d'une poudre P1 de UO 2 et d'une poudre P2 de PuO 2 ou de ThO 2 , b) le tamisage de ce mélange, c) la préparation d'un mélange final de poudres par dilution du tamisat avec une poudre P3 de UO 2 , d) le pastillage de ce mélange final et e) le frittage des pastilles, et dans lequel on incorpore au moins un composé choisi parmi les oxydes de Cr, Al, Ti, Mg, Va et de Nb, leurs précurseurs et les composés inorganiques aptes à apporter l’élément soufre au cours de l’étape e), à au moins l’une des poudres P1, P2 et P3 et /ou au moins l’un des mélanges primaire ou final de poudres.

公开(公告)号：WO2005031756A1

公开(公告)日：2005-04-07

申请号：PCT/RU2003/000422

申请日：2003-09-29

IPC: G21C3/62

CPC classification number: G21C21/02 ,  G21C3/62 ,  G21Y2002/201 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/38

Abstract: The invention relates to nuclear engineering. The inventive method for producing ceramic nuclear fuel tablets consists in preparing, granulating and pressing a moulding powder and in sintering the thus obtained tablets. The preparation stage consisting in grinding and mixing is carried out by means of ferromagnetic needles (7) in a container (4) under magnetic field action. The inventive device for preparing the moulding powder comprises a protective chamber (12), a grinding and mixing unit embodied in the form of an inductor coil (10). A tube (9) which is made of a non-magnetic material and in which the container (4) is arranged is introduced into the inductor coil (10). Said device also comprises a powder granulation unit, a container conveying and positioning system provided with elements for vertically displacing (8, 13) and turning (14) said container. The protective chamber (12) is embodied in the form of a circuit in such a way that the container (4) is displaceable therein. Said container (4) is made of a non-magnetic material in the form of a cylinder and provided on the end surface thereof with a valve (6) which is connected to a cylindrical tank (21) by means of a flange joint (25a, 25b). The valve (6) has an internal cavity which is separated from the cylindrical tank by a transversal mesh partition (26) impenetrable for the ferromagnetic needles (7). Said invention is characterised in that it improves the powder mixing efficiency.

Abstract translation: 本发明涉及核工程。 制造陶瓷核燃料片的本发明的方法在于制备造粒和压制成型粉末并烧结由此获得的片剂。 由研磨和混合组成的制备阶段通过铁磁性针（7）在容器（4）中的磁场作用下进行。 用于制备模制粉末的本发明的装置包括保护室（12），以电感线圈（10）的形式实现的研磨和混合单元。 将由非磁性材料制成的容器（4）的管（9）引入到电感线圈（10）中。 所述装置还包括粉末造粒单元，容器输送和定位系统，其具有用于垂直移位（8,13）和转动（14）所述容器的元件。 保护室（12）以电路的形式实现，使得容器（4）可在其中移动。 所述容器（4）由气缸形式的非磁性材料制成，并在其端面上设置有阀（6），阀（6）通过法兰接头（25a）连接到圆筒形容器 ，25b）。 阀（6）具有内腔，其通过不能穿过铁磁针（7）的横向网格隔板（26）与圆柱形罐隔开。 本发明的特征在于其提高粉末混合效率。

公开(公告)号：WO03017287A3

公开(公告)日：2003-05-01

申请号：PCT/GB0203823

申请日：2002-08-19

Applicant: BNFL IP LTD ,  PARKER ROSS STRACHEN ,  BRADLEY MICHAEL

Inventor： PARKER ROSS STRACHEN ,  BRADLEY MICHAEL

IPC: G21C3/62 ,  G21F7/005

CPC classification number: G21C3/623 ,  G21F7/005 ,  Y02E30/38

Abstract: A method of containing contaminating material, feed material handling apparatus and the use of feed material handling apparatus is provided with a view to minimising the possibilities for contaminating material spreading from a high contamination level environment to a low contamination level environment, the two environments being linked by a passage, at least part of the passage being filled with the feed material.

Abstract translation: 提供一种容纳污染物质，给料处理装置和使用给料处理装置的方法，以使污染物质从高污染等级环境扩散到低污染等级环境的可能性最小化，两个环境相关联 通过通道，通道的至少一部分填充有供给材料。

公开(公告)号：WO2003005375A1

公开(公告)日：2003-01-16

申请号：PCT/FR2002/002301

申请日：2002-07-02

Applicant: COMMISSARIAT A L'ENERGIE ATOMIQUE ,  COMPAGNIE GENERALE DES MATIERES NUCLEAIRES ,  GOTTA, Marie-Jeanne ,  TOURY, Grégoire ,  TROTABAS, Maria

Inventor： GOTTA, Marie-Jeanne ,  TOURY, Grégoire ,  TROTABAS, Maria

IPC: G21C3/62

CPC classification number: G21C3/623 ,  Y02E30/38

Abstract: L'invention se rapporte à un procédé de fabrication d'un matériau composite constitué d'amas d'un mélange de UO 2 et de PuO 2 dispersés dans une matrice de UO 2 comprenant les étapes de co-broyage à sec d'une poudre de UO 2 et d'une poudre de PuO 2 de façon à obtenir un mélange primaire homogène, de consolidation du mélange primaire de façon à obtenir des amas cohésifs, de tamisage des amas entre 20 et 350 μm, de dilution des amas tamisés dans une matrice de UO 2 de façon à obtenir un mélange de poudres, de pastillage du mélange de poudres, et de frittage des pastilles obtenues de façon à obtenir le composite.

Abstract translation: 本发明涉及一种制备复合材料的方法，所述复合材料由分散在UO> 2 <基体中的UO 2>和PuO 2 <混合物的混合物组成，包括步骤，U0> 2 <粉末和 将PuO> 2 <粉末，以获得均匀的初级混合物，将初级混合物固结，得到粘结聚集体，筛分20〜350μm的聚集体，将筛分的聚集体稀释至UO> 2 < 得到粉末混合物，将粉末混合物造粒，并烧结得到的粒料，得到复合材料。

公开(公告)号：WO2003005374A1

公开(公告)日：2003-01-16

申请号：PCT/FR2002/002285

申请日：2002-07-01

Applicant: COMMISSARIAT A L'ENERGIE ATOMIQUE ,  COMPAGNIE GENERALE DES MATIERES NUCLEAIRES ,  CARANONI, Laurent ,  DUBOIS, Sylvie

Inventor： CARANONI, Laurent ,  DUBOIS, Sylvie

IPC: G21C3/62

CPC classification number: G21C3/623 ,  Y02E30/38

Abstract: Procédé de sulfuration d'une poudre d'UO 2 , dans lequel ladite poudre est sulfurée par mise en contact avec un agent de sulfuration gazeux.Procédé de fabrication de pastilles de combustible nucléaire ô base d'oxyde d'uranium, ou d'oxyde mixte d'uranium et de plutonium, ô partir d'une charge totalement ou partiellement soufrée de poudre d'UO 2 ou de poudre d'UO 2 et de PuO 2 , par lubrification, pastillage et frittage, dans lequel : la charge de poudre soumise ô la lubrification, au pastillage et au frittage est préparée par les étapes successives suivantes : - on réalise la sulfuration d'une poudre de UO 2 par le procédé de sulfuration ci-dessus ; - on mélange éventuellement ladite poudre soufrée dans une matrice constituée d'une poudre d'UO 2 , ou d'une poudre d'UO 2 et d'une poudre de PuO 2 ; et, on soumet ladite charge, formée de ladite poudre soufrée ou dudit mélange, aux opérations de lubrification, de pastillage et de frittage.

Abstract translation: 本发明涉及一种用于硫化UO 2粉末的方法，其中所述粉末通过与气体硫化剂接触而被硫化。 本发明还涉及一种制备基于氧化铀的核燃料颗粒的方法，或者是通过润滑来制备完全或部分硫化的UO> 2 <粉末或UO> 2 <和PuO> 2 <粉末的原料的混合铀和钚氧化物 造粒和烧结，其中包括制备要润滑，造粒和烧结的粉末，步骤如下：通过上述硫化方法硫化UO> 2 <粉末; 任选地将所述硫化粉末以由UO> 2 <粉末或UO> 2 <粉末和PuO 2 <粉末组成的基质混合; 并将由所述硫化粉末或所述混合物组成的所述进料进行润滑，造粒和烧结。

公开(公告)号：WO01050477A1

公开(公告)日：2001-07-12

申请号：PCT/GB2001/000033

申请日：2001-01-05

IPC: G21C3/62 ,  G21C3/328 ,  G21C7/00 ,  G21C3/28

CPC classification number: G21C7/005 ,  G21C3/328 ,  G21Y2002/201 ,  G21Y2002/302 ,  G21Y2004/30 ,  Y02E30/38 ,  Y02E30/39

Abstract: The invention provides fuel assemblies and reactor cores assembled from them which offer improved reactor performance and/or burnup rates and/or ease of manufacture. In particular, the invention provides a mixed oxide fuel assembly for a nuclear reactor in which the fuel assembly comprises a plurality of fuel rods, a largest diameter fuel rod type, a smallest diameter fuel rod type, and one or more intermediate size fuel rod types being provided, between 25 % and 100 % of the peripheral fuel rods being provided of the intermediate size or sizes fuel rod type, the corner rods of the fuel assembly being of the smallest size fuel rod type.

Abstract translation: 本发明提供了从它们组装的燃料组件和反应堆芯，其提供改进的反应器性能和/或燃耗速率和/或易于制造。 特别地，本发明提供了一种用于核反应堆的混合氧化物燃料组件，其中燃料组件包括多个燃料棒，最大直径燃料棒型，最小直径燃料棒型和一种或多种中等尺寸燃料棒类型 设置有25％至100％的外围燃料棒由中等尺寸或大小的燃料棒型提供，燃料组件的拐角杆为最小尺寸燃料棒型。

公开(公告)号：WO00042617A1

公开(公告)日：2000-07-20

申请号：PCT/EP1999/007495

申请日：1999-10-06

IPC: G21C3/62

CPC classification number: G21C3/623 ,  Y02E30/38

Abstract: A method for tailoring the density of nuclear fuel pellets so that the local microscopic density of the fuel in a pellet is greater than the overall density of the pellet, the method being based on prefabricated precursor beads. According to the method: a) a defined first quantity of precursor beads containing no Pu is thermally treated under an oxidising atmosphere at a temperature of below 1150 DEG C, b) a defined second quantity of precursor beads is thermally treated under a reducing atmosphere at a temperature of below 1150 DEG C, c) said treated first and second quantities are mixed and then pressed into green pellets, d) these pellets are treated under a reducing atmosphere and a temperature less than 1100 DEG C in order to reduce the overstoechimoetric component and then sintered at a temperature above 1600 DEG C. During this final step, the material derived from the first quantity converts into a lower oxidation state, thereby reducing its volume and creating microscopic voids which reduce the swelling of the pellets during operation in a reactor.

Abstract translation: 一种用于调整核燃料颗粒密度的方法，使得颗粒中燃料的局部微观密度大于颗粒的总体密度，该方法基于预制的前体珠。 根据以下方法：a）在低于1150℃的温度下，在氧化气氛下热定形含有不含Pu的限定的第一量的前体珠，b）将限定的第二量的前体珠在还原气氛下热处理 温度低于1150℃，c）将所述经处理的第一和第二量混合，然后压制成生球团矿，d）在还原气氛和低于1100℃的温度下处理这些颗粒，以减少过度吸附组分 然后在高于1600℃的温度下烧结。在该最终步骤期间，衍生自第一量的材料转化为较低的氧化态，从而减小其体积并产生微小空隙，其在反应器中操作期间减小颗粒的溶胀 。

公开(公告)号：WO00032517A1

公开(公告)日：2000-06-08

申请号：PCT/CA1999/001104

申请日：1999-11-19

IPC: C01G43/025 ,  G21C3/62

CPC classification number: C01G43/025 ,  C01P2004/32 ,  C01P2004/54 ,  C01P2006/80 ,  G21C3/623 ,  Y02E30/38

Abstract: Uranium trioxide is reduced to uranium dioxide using microwave radiation or radiofrequency radiation directed in such a way that the radiation encounters an interface between uranium trioxide and the uranium-containing reduction product without first having passed through that product. By this method, and also using a reducing gas, it is possible to obtain UO2 with an O:U ratio less than 2.04:1.

Abstract translation: 使用微波辐射或射频辐射将三氧化铀还原成二氧化铀，使得辐射在没有首先通过该产物的情况下遇到三氧化铀和含铀还原产物之间的界面。 通过该方法，并且还使用还原气体，可以获得O：U比小于2.04:1的UO2。

公开(公告)号：WO2022225611A2

公开(公告)日：2022-10-27

申请号：PCT/US2022/018036

申请日：2022-02-25

Applicant: OKLO INC.

Inventor： DEWITTE, Jacob

IPC: G21C3/62 ,  G21C21/02 ,  G21C3/626

Abstract: A nuclear fuel system (210), nuclear fuel particle (100), and method for operating a nuclear fuel system are disclosed. A nuclear fuel system includes a matrix (130) material and a plurality of fuel particles (100) disposed in the matrix material, each fuel particle comprising a fuel kernel (110) and a fuel coating (120) that covers a surface of the fuel kernel. The fuel kernel comprises a fissile material including one or more of uranium-233, uranium-235, or plutonium-239. The fuel coating is functionally graded in density. A density of the fuel coating increases along an outward radial direction referenced to the center of the fuel kernel. The fuel coating comprises a neutron moderating material. A volume fraction of fuel particles is thirty-five percent or more of a volume of a nuclear fuel compact.

公开(公告)号：WO2022081243A1

公开(公告)日：2022-04-21

申请号：PCT/US2021/045635

申请日：2021-08-12

Applicant: BWXT ADVANCED TECHNOLOGIES LLC ,  BWXT NUCLEAR ENERGY, INC.

Inventor： JOGERST, James D ,  BARRINGER, Eric A.

IPC: G21C3/62 ,  G21C3/64 ,  B64G1/40

Abstract: CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.