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:
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:
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:
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:
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:
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。
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:
A polymer composition includes a rubber modified vinyl resin, a cyclic alkyl phosphate compound, and an aromatic phosphate ester. Some embodiments may additionally comprises a polyphenylene ether resin. In some embodiments, the compositions have good flame retardancy, color stability, impact resistance, and thermal stability.