专利快速检索-快速检索全球专利，免费商用专利数据库-IPRDB

1. 发明授权

US07485246B2 Fabrication method of sintered duplex nuclear fuel pellet 失效
标题翻译：烧结双相核燃料颗粒的制备方法
公开(公告)号：US07485246B2
公开(公告)日：2009-02-03
申请号：US11049452
申请日：2005-02-02
申请人： Young Woo Rhee , Keon Sik Kim , Jong Hun Kim , Ki Won Kang , Jae Ho Yang , Kun Woo Song , Youn Ho Jung
发明人： Young Woo Rhee , Keon Sik Kim , Jong Hun Kim , Ki Won Kang , Jae Ho Yang , Kun Woo Song , Youn Ho Jung
IPC分类号： G21C21/00
CPC分类号： G21C21/02 , C22B1/2413 , G21Y2002/104 , G21Y2002/303 , G21Y2004/40
摘要： A method for fabricating a sintered duplex nuclear fuel pellet includes the steps of: preparing a first powder composed of a material selected from the group consisting of UO2 and UO2—Er2O3, and a second powder composed of UO2—Gd2O3 and a sintering additive; producing a duplex compact consisting of an annular outer portion composed of the first powder and a cylindrical inner portion composed of the second powder; and sintering the duplex compact under a reducing gas atmosphere, wherein the sintering additive contains manganese of 0.001% to 2% by weight based on the total weight of the cylindrical inner portion.
摘要翻译：一种烧结双相核燃料颗粒的制造方法包括以下步骤：制备由选自UO2和UO2-Er2O3的材料组成的第一粉末和由UO2-Gd2O3和烧结添加剂组成的第二粉末; 制造由第一粉末组成的环形外部部分和由第二粉末组成的圆筒形内部组成的双相压实体; 并在还原气体气氛下烧结所述双相压块，其中所述烧结添加剂含有基于所述圆筒形内部部分的总重量为0.001重量％至2重量％的锰。

2. 发明授权

US06881376B2 Nuclear fuel body including tungsten network and method of manufacturing the same 有权
标题翻译：包括钨网的核燃料体及其制造方法
公开(公告)号：US06881376B2
公开(公告)日：2005-04-19
申请号：US10677681
申请日：2003-10-02
申请人： Kun Woo Song , Jae Ho Yang , Keon Sik Kim , Ki Won Kang , Jong Hun Kim , Youn Ho Jung
发明人： Kun Woo Song , Jae Ho Yang , Keon Sik Kim , Ki Won Kang , Jong Hun Kim , Youn Ho Jung
IPC分类号： G21C3/62 , B22F3/00
CPC分类号： G21C3/623 , G21Y2002/104 , G21Y2004/10 , Y02E30/38
摘要： The present invention relates to a nuclear fuel body comprising tungsten network and a method for manufacturing the same, more particularly, a nuclear fuel body in which tungsten network is continuously formed over the entire or some parts of a sintered body and a method for manufacturing the same. The sintered body in the nuclear fuel body of the present invention contains tungsten network having excellent heat conductivity, leading to the enhancement of heat conductivity of the nuclear fuel sintered body itself with decreasing the temperature of the nuclear fuel, so that it can contribute to the improvement in safety and performance of nuclear fuel.
摘要翻译：本发明涉及一种包括钨网络的核燃料体及其制造方法，更具体地说，涉及在烧结体的全部或部分上连续形成钨网的核燃料体，相同。本发明的核燃料体中的烧结体含有具有优异导热性的钨网络，导致核燃料烧结体本身的导热性随着核燃料温度的降低而提高，从而可以有助于提高核燃料的安全和性能。

3. 发明申请

US20100051607A1 High-Frequency Inductive Heating Apparatus and Pressure-Less Sintering Method Using the Same 审中-公开
标题翻译：高频感应加热装置及其无压力烧结方法
公开(公告)号：US20100051607A1
公开(公告)日：2010-03-04
申请号：US12405008
申请日：2009-03-16
申请人： Jae Ho Yang , Jong Hun Kim , Ki Won Kang , Young Woo Rhee , Keon Sik Kim , Kun Woo Song
发明人： Jae Ho Yang , Jong Hun Kim , Ki Won Kang , Young Woo Rhee , Keon Sik Kim , Kun Woo Song
IPC分类号： H05B6/00
CPC分类号： H05B6/105
摘要： A high-frequency inductive heating apparatus of ceramic material, whereby the nonconductive ceramic specimen in which induced current is not generated at room temperature is rapidly heated in a preheating housing, and a pressure-less sintering method using the same, are disclosed. The high-frequency inductive heating apparatus includes a preheating housing placed in a chamber to preheat a ceramic material; an induction coil installed around the preheating housing for supplying induced current so that the preheating housing is heated; and a high-frequency current generator for supplying high-frequency current to the induction coil. According to the present invention, inductive heating is made possible of nonconductive ceramic material for which inductive heating has thus far been impossible because induced current is not generated at room temperature, so that rapid heating by the self-heating of the specimen of ceramic material is possible.
摘要翻译：公开了一种陶瓷材料的高频感应加热装置，其中在室温下不产生感应电流的非导电陶瓷样品在预热壳体中快速加热，并且公开了使用其的无压烧结方法。高频感应加热装置包括放置在腔室中以预热陶瓷材料的预热壳体; 安装在所述预热壳体周围的用于提供感应电流的感应线圈，以使所述预热壳体被加热; 以及用于向感应线圈提供高频电流的高频电流发生器。根据本发明，由于在室温下不产生感应电流，所以不可能进行感应加热的非导电陶瓷材料进行感应加热，因此通过陶瓷材料试样的自加热的快速加热是可能。

4. 发明授权

US08268204B2 Method for manufacturing sintered annular nuclear fuel pellet without surface grinding 有权
标题翻译：无表面磨削制造烧结环形核燃料颗粒的方法
公开(公告)号：US08268204B2
公开(公告)日：2012-09-18
申请号：US12552480
申请日：2009-09-02
申请人： Young Woo Rhee , Dong Joo Kim , Kun Woo Song , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Jae Ho Yang
发明人： Young Woo Rhee , Dong Joo Kim , Kun Woo Song , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Jae Ho Yang
IPC分类号： B22F3/12
CPC分类号： B30B11/02 , B22F2003/033 , B22F2998/00 , B22F2998/10 , B22F2999/00 , B28B3/027 , B30B15/022 , C04B35/51 , C04B2235/3284 , C04B2235/604 , C04B2235/608 , C04B2235/652 , C04B2235/6582 , C04B2235/77 , C04B2235/94 , C04B2235/9638 , G21C21/02 , G21C2003/045 , B22F5/106 , B22F1/007 , B22F3/02 , B22F3/1007 , B22F2201/013 , B22F2201/04 , B22F2201/05 , B22F2201/10
摘要： A method for manufacturing an annular nuclear fuel pellet is provided. In the method, an annular nuclear fuel green compact whose lateral cross-section is a trapezoid is prepared. The thickness of the annular nuclear fuel green compact reduces along one direction of the central axis, and a green density of the nuclear fuel green compact increases along one direction of the central axis. The annular nuclear fuel green compact is sintered under a reducing gas atmosphere so that the annular nuclear fuel pellet is obtained. According to this method, the annular pellet which has uniform inner and outer diameters and small diametric tolerances along the pellet height is fabricated without grinding the pellet surfaces.
摘要翻译：提供一种制造环形核燃料颗粒的方法。在该方法中，准备了横截面为梯形的环状核燃料生坯。环形核燃料生坯的厚度沿着中心轴的一个方向减小，并且核燃料生坯的绿色密度沿着中心轴的一个方向增加。环形核燃料生坯在还原气氛下烧结，得到环状核燃料颗粒。根据该方法，在不研磨颗粒表面的情况下制造具有均匀的内径和外径均匀且小颗粒高度的小直径公差的环形颗粒。

5. 发明申请

US20100254847A1 METHOD FOR MANUFACTURING SINTERED ANNULAR NUCLEAR FUEL PELLET WITHOUT SURFACE GRINDING 有权
标题翻译：无表面磨削的烧结球状核燃料粒子的制造方法
公开(公告)号：US20100254847A1
公开(公告)日：2010-10-07
申请号：US12552480
申请日：2009-09-02
申请人： Young Woo Rhee , Dong Joo Kim , Kun Woo Song , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Jae Ho Yang
发明人： Young Woo Rhee , Dong Joo Kim , Kun Woo Song , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Jae Ho Yang
IPC分类号： B22F3/12 , B22F1/00
CPC分类号： B30B11/02 , B22F2003/033 , B22F2998/00 , B22F2998/10 , B22F2999/00 , B28B3/027 , B30B15/022 , C04B35/51 , C04B2235/3284 , C04B2235/604 , C04B2235/608 , C04B2235/652 , C04B2235/6582 , C04B2235/77 , C04B2235/94 , C04B2235/9638 , G21C21/02 , G21C2003/045 , B22F5/106 , B22F1/007 , B22F3/02 , B22F3/1007 , B22F2201/013 , B22F2201/04 , B22F2201/05 , B22F2201/10
摘要： A method for manufacturing an annular nuclear fuel pellet is provided. In the method, an annular nuclear fuel green compact whose lateral cross-section is a trapezoid is prepared. The thickness of the annular nuclear fuel green compact reduces along one direction of the central axis, and a green density of the nuclear fuel green compact increases along one direction of the central axis. The annular nuclear fuel green compact is sintered under a reducing gas atmosphere so that the annular nuclear fuel pellet is obtained. According to this method, the annular pellet which has uniform inner and outer diameters and small diametric tolerances along the pellet height is fabricated without grinding the pellet surfaces.
摘要翻译：提供一种制造环形核燃料颗粒的方法。在该方法中，准备了横截面为梯形的环状核燃料生坯。环形核燃料生坯的厚度沿着中心轴的一个方向减小，并且核燃料生坯的绿色密度沿着中心轴的一个方向增加。环形核燃料生坯在还原气氛下烧结，得到环状核燃料颗粒。根据该方法，在不研磨颗粒表面的情况下制造具有均匀的内径和外径均匀且小颗粒高度的小直径公差的环形颗粒。

6. 发明授权

US08449795B2 Method of manufacturing sinter-active U3O8 powder and method of producing nuclear fuel pellets utilizing the same 有权
标题翻译：烧结活性U3O8粉末的制造方法以及使用其的制造核燃料粒子的方法
公开(公告)号：US08449795B2
公开(公告)日：2013-05-28
申请号：US11947502
申请日：2007-11-29
申请人： Jae Ho Yang , Young Woo Rhee , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Kun Woo Song
发明人： Jae Ho Yang , Young Woo Rhee , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Kun Woo Song
IPC分类号： G21C21/00 , C01G43/01 , C01G43/025
CPC分类号： G21C3/623 , G21C3/62 , G21C21/02 , Y02E30/38
摘要： There is provided a method of producing U3O8 powder having large surface area and small particle size by oxidizing defective UO2 pellets and manufacturing nuclear fuel pellets which are stable in a pore structure and high in density through the use of a mixture comprising UO2 powder and U3O8 powder. The method includes producing an U308 powder having a surface area of at least 1 m2/g by oxidizing defective UO2 pellets at a temperature of 300 to 370° C. in such a way that a maximum weight increase rate per 1 g of the UO2 pellets is up to 0.06 wt %/min; producing a mixed powder by mixing the U3O8 powder with an UO2 powder by 2 to 15 wt %; producing a compact by compression molding the mixed powder; and sintering the compact in a reducing gas atmosphere at a temperature of 1600 to 1800° C. In addition, a small amount of an Al-compound may be added to the oxidized U3O8 powder before the U3O8 powder is mixed with the UO2 powder. The additive such as Al is mixed with the U3O8 powder and then mixed with the UO2 powder to produce the pellets by a conventional production method. This ensures a stable pore structure, high density and a considerable increase in a crystal grain size.
摘要翻译：提供一种通过氧化不良UO 2颗粒并制造核孔结构稳定且密度高的核燃料颗粒，通过使用包含UO 2粉末和U 3 O 8粉末的混合物制备具有大表面积和小粒径的U3O8粉末的方法。该方法包括通过在300-370℃的温度下氧化有缺陷的UO 2颗粒来生产表面积至少为1m 2 / g的U308粉末，使得每1g UO 2颗粒的最大重量增加率高达0.06重量％/分钟; 通过将U3O8粉末与UO2粉末混合2〜15重量％来制造混合粉末; 通过压缩混合粉末制造压块; 并在1600〜1800℃的还原气体气氛中烧结。另外，在U 3 O 8粉末与UO 2粉末混合之前，可以向氧化的U3O8粉末中添加少量Al化合物。将诸如Al的添加剂与U3O8粉末混合，然后与UO 2粉末混合以通过常规生产方法制备颗粒。这确保了稳定的孔结构，高密度和晶粒尺寸的显着增加。

7. 发明申请

US20080185743A1 METHOD OF MANUFACTURING SINTER-ACTIVE U3O8 POWDER AND METHOD OF PRODUCING NUCLEAR FUEL PELLETS UTILIZING THE SAME 有权
标题翻译：制造烧结活性U3O8粉末的方法及使用其制造核燃料粒子的方法
公开(公告)号：US20080185743A1
公开(公告)日：2008-08-07
申请号：US11947502
申请日：2007-11-29
申请人： Jae Ho Yang , Young Woo Rhee , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Kun Woo Song
发明人： Jae Ho Yang , Young Woo Rhee , Ki Won Kang , Jong Hun Kim , Keon Sik Kim , Kun Woo Song
IPC分类号： G21C21/02
CPC分类号： G21C3/623 , G21C3/62 , G21C21/02 , Y02E30/38
摘要： There is provided a method of producing U3O8 powder having large surface area and small particle size by oxidizing defective UO2 pellets and manufacturing nuclear fuel pellets which are stable in a pore structure and high in density through the use of a mixture comprising UO2 powder and U3O8 powder. The method includes producing an U308 powder having a surface area of at least 1 m2/g by oxidizing defective UO2 pellets at a temperature of 300 to 370□ in such a way that a maximum weight increase rate per 1 g of the UO2 pellets is up to 0.06 wt %/min; producing a mixed powder by mixing the U3O8 powder with an UO2 powder by 2 to 15 wt %; producing a compact by compression molding the mixed powder; and sintering the compact in a reducing gas atmosphere at a temperature of 1600 to 1800□. In addition, a small amount of an Al-compound may be added to the oxidized U3O8 powder before the U3O8 powder is mixed with the UO2 powder. The additive such as Al is mixed with the U3O8 powder and then mixed with the UO2 powder to produce the pellets by a conventional production method. This ensures a stable pore structure, high density and a considerable increase in a crystal grain size.
摘要翻译：提供了通过氧化有缺陷的UO 2 N 2颗粒并制造核的方法制备具有大的表面积和小的粒度的U 3 O 8 N 8 通过使用包含二氧化钛粉末和U 3 O 8粉末的混合物的孔结构稳定且密度高的燃料颗粒。该方法包括通过在300〜370℃的温度下氧化不良的UO 2/2小球，制造表面积至少为1m 2 / g以上的U308粉末，相对于每1g NiO 2颗粒的最大重量增加速率高达0.06wt％/ min; 通过将U 3 N 2 O 3粉末与UO 2 N 2粉末混合2至15重量％来制备混合粉末; 通过压缩混合粉末制造压块; 并在1600〜1800℃的温度下在还原气体气氛中烧结。另外，在U 3 N 3 O 3上的少量Al化合物可以加入到氧化的N 3 O 8 O 8粉末中 > 8粉末与UO 2 N 2粉末混合。将诸如Al的添加剂与U 3 N 8 O 8粉末混合，然后与UO 2 N 2粉末混合以通过常规的生产方式。这确保了稳定的孔结构，高密度和晶粒尺寸的显着增加。

8. 发明授权

US08989340B2 Uranium dioxide nuclear fuel containing Mn and Al as additives and method of fabricating the same 有权
标题翻译：含有Mn和Al的二氧化铀核燃料作为添加剂及其制造方法
公开(公告)号：US08989340B2
公开(公告)日：2015-03-24
申请号：US12544497
申请日：2009-08-20
申请人： Ki Won Kang , Jae Ho Yang , Keon Sik Kim , Young Woo Rhee , Jong Hun Kim , Kun Woo Song
发明人： Ki Won Kang , Jae Ho Yang , Keon Sik Kim , Young Woo Rhee , Jong Hun Kim , Kun Woo Song
IPC分类号： G21C3/00 , G21C3/04 , G21C3/62 , G21C3/18 , G21C3/17 , G21C3/58 , G21C21/00
CPC分类号： G21C3/04 , G21C3/17 , G21C3/18 , G21C3/58 , G21C3/623 , G21C21/00 , Y02E30/38 , Y02E30/40
摘要： UO2 nuclear fuel pellets are fabricated by adding additive powder comprising Mn compound and Al compound into UO2 powder.
摘要翻译：通过将包含Mn化合物和Al化合物的添加剂粉末添加到UO 2粉末中来制造UO2核燃料颗粒。

9. 发明申请

US20130240805A1 Uranium Dioxide Nuclear Fuel Containing Mn and Al as Additives and Method of Fabricating the Same 有权
标题翻译：含有Mn和Al的二氧化铀核燃料作为添加剂及其制造方法
公开(公告)号：US20130240805A1
公开(公告)日：2013-09-19
申请号：US12544497
申请日：2009-08-20
申请人： Ki Won Kang , Jae Ho Yang , Keon Sik Kim , Young Woo Rhee , Jong Hun Kim , Kun Woo Song
发明人： Ki Won Kang , Jae Ho Yang , Keon Sik Kim , Young Woo Rhee , Jong Hun Kim , Kun Woo Song
IPC分类号： G21C3/04
CPC分类号： G21C3/04 , G21C3/17 , G21C3/18 , G21C3/58 , G21C3/623 , G21C21/00 , Y02E30/38 , Y02E30/40
摘要： UO2 nuclear fuel pellets are fabricated by adding additive powder comprising Mn compound and Al compound into UO2 powder.
摘要翻译：通过将包含Mn化合物和Al化合物的添加剂粉末添加到UO 2粉末中来制造UO2核燃料颗粒。

你已经成功收藏专利！

检索式保存成功!

IPRDB

热门服务

关于我们

友情链接

联系方式