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    Method of manufacturing large-grained uranium dioxide fuel pellets containing U3O8
    1.
    发明授权
    Method of manufacturing large-grained uranium dioxide fuel pellets containing U3O8 失效
    制造含有U3O8的大颗粒二氧化铀燃料颗粒的方法

    公开(公告)号：US06251309B1

    公开(公告)日：2001-06-26

    申请号：US09357169

    申请日：1999-07-19

    申请人： Kun-Woo Song ,  Keon-Sik Kim ,  Ki-Won Kang ,  Jong-Hun Kim ,  Youn-Ho Jung

    发明人： Kun-Woo Song ,  Keon-Sik Kim ,  Ki-Won Kang ,  Jong-Hun Kim ,  Youn-Ho Jung

    IPC分类号： G21G400

    CPC分类号： G21C3/623 ,  G21C21/02 ,  G21Y2002/302 ,  G21Y2002/304 ,  G21Y2004/40 ,  G21Y2004/60 ,  Y02E30/38

    摘要： Disclosed is a method of manufacturing large-grained uranium dioxide pellets through the use of U3O8 single crystals. The method consists of two main steps; producing U3O8 single crystals and manufacturing large-grained UO2 pellets. The U3O8 single crystals are produced by annealing U3O8 powder to make U3O8 polycrystalline aggregates having a large crystal size, and by dividing the U3O8 polycrystalline aggregate into its constituent U3O8 single crystals. Large-grained UO2 pellets are produced by forming a mixture comprising UO2 powder and the U3O8 single crystals, making granules of the mixture, pressing the granules into green pellets, and sintering the green pellets above 1600° C. for more than one hour in a reducing gas. The U3O8 powder is produced preferably by heating defective UO2 pellets in air to oxidize UO2 to U3O8. The invention provides a method of manufacturing a large-grained UO2 pellet with defective pellets reused.

    摘要翻译： 公开了通过使用U3O8单晶制造大粒径二氧化铀颗粒的方法。 该方法由两个主要步骤组成： 生产U3O8单晶并制造大粒度UO2颗粒。 U3O8单晶通过退火U3O8粉末制成具有大晶体尺寸的U3O8多晶聚集体，并将U3O8多晶聚集体分成其组成的U3O8单晶。 通过形成包含UO 2粉末和U 3 O 8单晶的混合物来制备大粒度的UO2颗粒，制备混合物的颗粒，将颗粒压成生球团矿，并将生坯颗粒在1600℃以上烧结超过1小时 减少气体。 U3O8粉末优选通过在空气中加热有缺陷的UO 2颗粒而氧化U 2 O至U 3 O 8。 本发明提供一种制造具有有缺陷的颗粒的大颗粒UO2颗粒的方法。

    Method for Preparing Sintered Annular Nuclear Fuel Pellet
    4.
    发明申请
    Method for Preparing Sintered Annular Nuclear Fuel Pellet 有权
    烧结环形核燃料颗粒的制备方法

    公开(公告)号：US20110049734A1

    公开(公告)日：2011-03-03

    申请号：US12871146

    申请日：2010-08-30

    申请人： Young-Woo Rhee ,  Dong-Joo Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Keon-Sik Kim ,  Jae-Ho Yang ,  Ki-Won Kang ,  Chill Sun Ryu

    发明人： Young-Woo Rhee ,  Dong-Joo Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Keon-Sik Kim ,  Jae-Ho Yang ,  Ki-Won Kang ,  Chill Sun Ryu

    IPC分类号： G21C21/02

    CPC分类号： G21C21/02

    摘要： A method for fabricating a sintered annular nuclear fuel pellet includes molding nuclear fuel powder or granule, an oxide of a fissile element (M), to fabricate an annular nuclear fuel green body. A rod-like shaped structure is inserted into the annular nuclear fuel green body and sintered in a slight oxidizing gas atmosphere such that the oxide of the fissile element has a balanced O/M ratio higher than a desired O/M ratio (oxygen/fissile element) of a final sintered annular nuclear fuel pellet, while being maintained in a cubic phase. The sintered annular nuclear fuel pellet is then reduced in a reductive gas atmosphere so as to have the desired O/M ratio in the state that the rod-like shaped structure is inserted.

    摘要翻译： 一种烧结环形核燃料颗粒的制造方法，包括成型核燃料粉末或颗粒，易裂变元素（M）的氧化物，以制造环形核燃料生坯。 棒形结构被插入到环形核燃料生坯中并在轻微的氧化气体气氛中烧结，使得易裂变元素的氧化物具有高于所需O / M比的平衡O / M比（氧/裂变 元素）的最终烧结环形核燃料颗粒，同时保持立方相。 然后将烧结的环形核燃料颗粒在还原性气体气氛中还原，以便在棒状结构被插入的状态下具有所需的O / M比。

    Method for recycling fuel scrap into manufacture of nuclear fuel pellets
    5.
    发明授权
    Method for recycling fuel scrap into manufacture of nuclear fuel pellets 失效
    将燃料废料回收用于制造核燃料颗粒的方法

    公开(公告)号：US5882552A

    公开(公告)日：1999-03-16

    申请号：US932602

    申请日：1997-09-17

    申请人： Kun-Woo Song ,  Keon-Sik Kim ,  Jong-Hun Kim ,  Youn-Ho Jung

    发明人： Kun-Woo Song ,  Keon-Sik Kim ,  Jong-Hun Kim ,  Youn-Ho Jung

    IPC分类号： G21C3/33 ,  C01G43/025 ,  C01G56/00 ,  G21C3/62 ,  G21C21/02 ,  G21C21/00

    CPC分类号： G21C3/623 ,  C01G43/025 ,  C01G56/00 ,  C01P2002/54 ,  C01P2004/61 ,  C01P2006/10 ,  Y02E30/38

    摘要： A method is disclosed in which fuel scrap of UO.sub.2 alone or UO.sub.2 containing an oxide of plutonium, gadolinium or erbium is recycled into the manufacture of nuclear fuel pellets. The fuel scrap consisting of defective fuel pellets is comminuted through oxidation to fuel particles of U.sub.3 O.sub.8 alone or U.sub.3 O.sub.8 containing an oxide of plutonium, gadolinium or erbium, and a sintering aid containing an element selected from the group consisting of aluminum, magnesium, niobium, titanium, vanadium, chromium, lithium, silicon, tin and mixtures thereof is added in a quantity of about 0.02% to about 2% by weight to the sintering powder which consists of said recycled fuel particles and fresh fuel powder having a composition of UO.sub.2 alone or UO.sub.2 in a mixture of PuO.sub.2, Gd.sub.2 O.sub.3 or Er.sub.2 O.sub.3. The sintering powder is then mixed uniformly, in which the amount of the recycled fuel particles is in the range of about 10% to about 100% by weight. Green pellets are made by pressing the sintering powder and then sintered at about 1500.degree. C. to about 1800.degree. C. in a reducing atmosphere to produce new fuel pellets.

    摘要翻译： 公开了一种方法，其中单独的UO2的燃料废料或含有钚，钆或铒的氧化物的UO2被再循环到核燃料颗粒的制造中。 由有缺陷的燃料颗粒组成的燃料废料通过氧化粉碎成单独的U3O8的燃料颗粒或含有钚，钆或铒氧化物的U3O8，以及含有选自铝，镁，铌，钛的元素的烧结助剂 ，钒，铬，锂，硅，锡及其混合物的量以约0.02重量％至约2重量％的量加入到由所述再循环燃料颗粒和具有单独的UO2组成的新鲜燃料粉末组成的烧结粉末 UO2在PuO2，Gd2O3或Er2O3的混合物中。 然后将烧结粉末均匀混合，其中再循环燃料颗粒的量在约10重量％至约100重量％的范围内。 通过压制烧结粉末然后在还原气氛中在约1500℃至约1800℃下烧结生成颗粒，以产生新的燃料颗粒。

    Method of manufacturing a nuclear fuel pellet by recycling an irradiated oxide fuel pellet
    6.
    发明授权
    Method of manufacturing a nuclear fuel pellet by recycling an irradiated oxide fuel pellet 失效
    通过再循环照射的氧化物燃料颗粒来制造核燃料颗粒的方法

    公开(公告)号：US06251310B1

    公开(公告)日：2001-06-26

    申请号：US09201146

    申请日：1998-11-30

    申请人： Kun-Woo Song ,  Keon-Sik Kim ,  Youn-Ho Jung ,  Myung-Seung Yang

    发明人： Kun-Woo Song ,  Keon-Sik Kim ,  Youn-Ho Jung ,  Myung-Seung Yang

    IPC分类号： G21C2100

    CPC分类号： G21C21/00

    摘要： A method of manufacturing new UO2-based fuel pellets by recycling irradiated UO2-based fuel pellets. Irradiated UO2-based fuel pellets are oxidized so as to make U3O8-based powder, and then the U3O8 -based powder is mixed with an additive which contains at least one oxide of an element selected from the group consisting of niobium, titanium, vanadium, aluminum, magnesium, chromium, silicon and lithium. Green pellets are formed from the mixed powder, and then sintered, preferably at 1500° C. or higher, in a reducing gas atmosphere to produce UO2-based fuel pellets with high densities.

    摘要翻译： 通过再循环照射的基于氧化物的燃料颗粒来制造新的基于氧化物的燃料颗粒的方法。 照射的基于氧化铝的燃料颗粒被氧化以制备U3O8基粉末，然后将基于U3O8的粉末与含有至少一种选自铌，钛，钒， 铝，镁，铬，硅和锂。 由混合粉末形成生球团矿，然后在还原气体气氛中优选在1500℃以上烧结，制成高密度的基于氧化物的燃料粒料。

    Method of controlling solubility of additives at and near grain boundaries, and method of manufacturing sintered nuclear fuel pellet having large grain size using the same
    7.
    发明授权
    Method of controlling solubility of additives at and near grain boundaries, and method of manufacturing sintered nuclear fuel pellet having large grain size using the same 有权
    控制添加剂在晶界处及其附近溶解度的方法，以及使用其制造具有大晶粒尺寸的烧结核燃料颗粒的方法

    公开(公告)号：US09190179B2

    公开(公告)日：2015-11-17

    申请号：US13275784

    申请日：2011-10-18

    申请人： Jae-Ho Yang ,  Keon-Sik Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Young-Woo Rhee ,  Dong-Joo Kim ,  Chill-Sun Ryu

    发明人： Jae-Ho Yang ,  Keon-Sik Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Young-Woo Rhee ,  Dong-Joo Kim ,  Chill-Sun Ryu

    IPC分类号： G21C21/00 ,  G21C21/02 ,  G21C3/62

    CPC分类号： G21C21/02 ,  G21C3/62 ,  G21C3/623 ,  Y02E30/38

    摘要： Provided are a method of controlling the compositional gradient and solubility of doped-additives at grain boundaries during sintering of a uranium-based oxide green pellet including the additives, and a method of manufacturing a sintered nuclear fuel pellet having a large grain size using the same. The grain boundary solubility of the doped-additives is maintained at a certain level by stepwise varying of an oxygen partial pressure during isothermal sintering of a uranium-based oxide green pellet including the additives. The method of manufacturing a sintered nuclear fuel pellet having a large grain size includes preparing additive mixed uranium oxide powder, forming an additive mixed uranium oxide green pellet using the mixed powder, heating the green pellet to a sintering temperature in a gas atmosphere having a low oxygen partial pressure, and sintering while a sintering gas atmosphere is changed to stepwise increase an oxygen partial pressure at the isothermal sintering temperature.

    摘要翻译： 提供了在包含添加剂的铀基氧化物生颗粒的烧结期间控制掺杂添加剂在晶界处的组成梯度和溶解度的方法，以及使用其制备具有大晶粒尺寸的烧结核燃料芯片的方法 。 掺杂添加剂的晶界溶解度通过在包括添加剂的铀基氧化物生颗粒的等温烧结期间逐步改变氧分压而保持在一定水平。 制造具有大粒径的烧结核燃料颗粒的方法包括制备添加剂混合氧化铀粉末，使用混合粉末形成添加剂混合的氧化铀颗粒，将生坯颗粒加热至低浓度的气体气氛中的烧结温度 氧分压和烧结，同时烧结气氛改变为在等温烧结温度下逐步增加氧分压。

    Method for preparing sintered annular nuclear fuel pellet
    9.
    发明授权
    Method for preparing sintered annular nuclear fuel pellet 有权
    烧结环形核燃料颗粒的制备方法

    公开(公告)号：US08585939B2

    公开(公告)日：2013-11-19

    申请号：US12871146

    申请日：2010-08-30

    申请人： Young-Woo Rhee ,  Dong-Joo Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Keon-Sik Kim ,  Jae-Ho Yang ,  Chill-Sun Ryu

    发明人： Young-Woo Rhee ,  Dong-Joo Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Keon-Sik Kim ,  Jae-Ho Yang ,  Ki-Won Kang

    IPC分类号： G21C21/00 ,  B28B21/00 ,  B28B3/00 ,  C04B33/32

    CPC分类号： G21C21/02

    摘要： A method for fabricating a sintered annular nuclear fuel pellet includes molding nuclear fuel powder or granule, an oxide of a fissile element (M), to fabricate an annular nuclear fuel green body. A rod-like shaped structure is inserted into the annular nuclear fuel green body and sintered in a slight oxidizing gas atmosphere such that the oxide of the fissile element has a balanced O/M ratio higher than a desired O/M ratio (oxygen/fissile element) of a final sintered annular nuclear fuel pellet, while being maintained in a cubic phase. The sintered annular nuclear fuel pellet is then reduced in a reductive gas atmosphere so as to have the desired O/M ratio in the state that the rod-like shaped structure is inserted.

    摘要翻译： 一种烧结环形核燃料颗粒的制造方法，包括成型核燃料粉末或颗粒，易裂变元素（M）的氧化物，以制造环形核燃料生坯。 棒形结构被插入到环形核燃料生坯中并在轻微的氧化气体气氛中烧结，使得易裂变元素的氧化物具有高于所需O / M比的平衡O / M比（氧/裂变 元素）的最终烧结环形核燃料颗粒，同时保持立方相。 然后将烧结的环形核燃料颗粒在还原性气体气氛中还原，以便在棒状结构被插入的状态下具有所需的O / M比。

    METHOD OF CONTROLLING SOLUBILITY OF ADDITIVES AT AND NEAR GRAIN BOUNDARIES, AND METHOD OF MANUFACTURING SINTERED NUCLEAR FUEL PELLET HAVING LARGE GRAIN SIZE USING THE SAME
    10.
    发明申请
    METHOD OF CONTROLLING SOLUBILITY OF ADDITIVES AT AND NEAR GRAIN BOUNDARIES, AND METHOD OF MANUFACTURING SINTERED NUCLEAR FUEL PELLET HAVING LARGE GRAIN SIZE USING THE SAME 有权
    控制添加剂在谷物边界附近的溶解性的方法以及使用其制造具有大颗粒尺寸的烧结核燃料片的方法

    公开(公告)号：US20120098149A1

    公开(公告)日：2012-04-26

    申请号：US13275784

    申请日：2011-10-18

    申请人： JAE-HO YANG ,  Keon-Sik Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Young-Woo Rhee ,  Dong-Joo Kim ,  Chill-Sun Ryu

    发明人： JAE-HO YANG ,  Keon-Sik Kim ,  Kun-Woo Song ,  Jong-Hun Kim ,  Young-Woo Rhee ,  Dong-Joo Kim ,  Chill-Sun Ryu

    IPC分类号： G21C21/00

    CPC分类号： G21C21/02 ,  G21C3/62 ,  G21C3/623 ,  Y02E30/38

    摘要： Provided are a method of controlling the compositional gradient and solubility of doped-additives at grain boundaries during sintering of a uranium-based oxide green pellet including the additives, and a method of manufacturing a sintered nuclear fuel pellet having a large grain size using the same. The grain boundary solubility of the doped-additives is maintained at a certain level by stepwise varying of an oxygen partial pressure during isothermal sintering of a uranium-based oxide green pellet including the additives. The method of manufacturing a sintered nuclear fuel pellet having a large grain size includes preparing additive mixed uranium oxide powder, forming an additive mixed uranium oxide green pellet using the mixed powder, heating the green pellet to a sintering temperature in a gas atmosphere having a low oxygen partial pressure, and sintering while a sintering gas atmosphere is changed to stepwise increase an oxygen partial pressure at the isothermal sintering temperature.

    摘要翻译： 提供一种在包含添加剂的铀基氧化物生颗粒的烧结期间控制掺杂添加剂在晶界处的组成梯度和溶解度的方法，以及使用其制备具有大晶粒尺寸的烧结核燃料芯片的方法 。 掺杂添加剂的晶界溶解度通过在包括添加剂的铀基氧化物生颗粒的等温烧结期间逐步改变氧分压而保持在一定水平。 制造具有大粒径的烧结核燃料颗粒的方法包括制备添加剂混合氧化铀粉末，使用混合粉末形成添加剂混合的氧化铀颗粒，将生坯颗粒加热至低浓度的气体气氛中的烧结温度 氧分压和烧结，同时烧结气氛改变为在等温烧结温度下逐步增加氧分压。