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1. 发明授权

US09666315B2 Method for reprocessing spent nuclear fuel and centrifugal extractor therefor 有权
公开(公告)号：US09666315B2
公开(公告)日：2017-05-30
申请号：US12533605
申请日：2009-07-31
申请人： Koji Mizuguchi , Reiko Fujita , Kouki Fuse , Hitoshi Nakamura , Kazuhiro Utsunomiya , Nobuhiko Tanaka
发明人： Koji Mizuguchi , Reiko Fujita , Kouki Fuse , Hitoshi Nakamura , Kazuhiro Utsunomiya , Nobuhiko Tanaka
IPC分类号： C02F1/38 , C25C1/00 , C25C7/00 , C25B15/00 , G21C19/46 , B01D11/04 , B01D17/02
CPC分类号： G21C19/46 , B01D11/0434 , B01D11/0492 , B01D17/0217 , B01D17/047 , B01D17/06 , Y02W30/883
摘要： A spent nuclear fuel is reprocessed by dissolving a spent nuclear fuel in an aqueous nitric acid solution and separating and recovering nuclides contained in the resulting fuel solution by solvent extraction. A spent nuclear fuel reprocessing method includes: an electrolytic valence adjustment step in which nuclides contained in the fuel solution is electrolytically reduced without removing fission products or minor actinides until valence of plutonium is at a level at which solvent extraction efficiency is low by using the valence of plutonium contained in the fuel solution as a parameter; and a nuclide separation step in which, by using an extraction solvent which extracts uranium contained in the fuel solution, uranium is distributed from the fuel solution subjected to the electrolytic valence adjustment step to the extraction solvent.

2. 发明申请

US20100038249A1 METHOD FOR REPROCESSING SPENT NUCLEAR FUEL AND CENTRIFUGAL EXTRACTOR THEREFOR 有权
标题翻译：替代燃料核燃料和离心机的方法
公开(公告)号：US20100038249A1
公开(公告)日：2010-02-18
申请号：US12533605
申请日：2009-07-31
申请人： Koji Mizuguchi , Reiko Fujita , Kouki Fuse , Hitoshi Nakamura , Kazuhiro Utsunomiya , Nobuhiko Tanaka
发明人： Koji Mizuguchi , Reiko Fujita , Kouki Fuse , Hitoshi Nakamura , Kazuhiro Utsunomiya , Nobuhiko Tanaka
IPC分类号： C25C1/22 , C25B15/00
CPC分类号： G21C19/46 , B01D11/0434 , B01D11/0492 , B01D17/0217 , B01D17/047 , B01D17/06 , Y02W30/883
摘要： A spent nuclear fuel is reprocessed by dissolving a spent nuclear fuel in an aqueous nitric acid solution and separating and recovering nuclides contained in the resulting fuel solution by solvent extraction. A spent nuclear fuel reprocessing method includes: an electrolytic valence adjustment step in which nuclides contained in the fuel solution is electrolytically reduced without removing fission products or minor actinides until valence of plutonium is at a level at which solvent extraction efficiency is low by using the valence of plutonium contained in the fuel solution as a parameter; and a nuclide separation step in which, by using an extraction solvent which extracts uranium contained in the fuel solution, uranium is distributed from the fuel solution subjected to the electrolytic valence adjustment step to the extraction solvent.
摘要翻译：废核燃料通过将废核燃料溶解在硝酸水溶液中并通过溶剂萃取分离和回收包含在所得燃料溶液中的核素来再处理。废核燃料后处理方法包括：电解质价调节步骤，其中包含在燃料溶液中的核素电解还原而不除去裂变产物或次要锕系元素，直到钚的价数处于使溶剂萃取效率低的水平时燃料溶液中所含的钚作为参数; 和核素分离步骤，其中通过使用提取燃料溶液中所含的铀的提取溶剂，将铀从经过电解质量调节步骤的燃料溶液分配到萃取溶剂中。

3. 发明授权

US09315915B2 Method for manufacturing zirconium metal and hafnium metal 有权
标题翻译：锆金属和铪金属的制造方法
公开(公告)号：US09315915B2
公开(公告)日：2016-04-19
申请号：US13001870
申请日：2009-06-29
申请人： Reiko Fujita , Koji Mizuguchi , Hitoshi Nakamura , Kouki Fuse , Mitsuru Kawamoto , Masaru Ito
发明人： Reiko Fujita , Koji Mizuguchi , Hitoshi Nakamura , Kouki Fuse , Mitsuru Kawamoto , Masaru Ito
IPC分类号： C25C3/00 , C22B5/00 , C25C3/26 , C22B34/14 , C22B34/12
CPC分类号： C25C3/26 , C22B34/1222 , C22B34/129 , C22B34/14 , Y02P10/23
摘要： An object of the present invention is to provide a method of producing metal zirconium, the method having a fewer steps and a smaller amount of secondary wastes generated, wherein the metal zirconium is obtained from a zirconium compound containing hafnium. A method of producing metal zirconium according to the present invention includes: a separation step of separating a hafnium oxychloride from a first substance containing a zirconium oxychloride and a hafnium oxychloride to obtain a second substance having a higher content of the zirconium oxychloride; a calcination step of calcining the second substance to obtain a third substance containing at least any of a zirconium oxychloride and a zirconium oxide; and a direct reduction step of holding the third substance in a molten salt with the third substance brought into contact with a cathode and applying a voltage between the cathode and an anode to directly reduce the third substance to obtain metal zirconium.
摘要翻译：本发明的目的是提供一种生产金属锆的方法，该方法具有较少的步骤和较少量的二次废弃物，其中金属锆由含有铪的锆化合物获得。根据本发明的金属锆的制造方法包括：从含有氯氧化锆和氯化铪的第一物质中分离氯氧化铪的分离工序，得到氯氧化锆含量较高的第二物质; 煅烧第二物质以获得含有三氯氧化锆和氧化锆中的至少一种的第三物质的煅烧步骤; 以及将第三物质保持在与第一物质接触的第三物质与阴极接触并在阴极和阳极之间施加电压以直接还原第三物质以获得金属锆的直接还原步骤。

4. 发明申请

US20110108434A1 METHOD OF PRODUCING METAL ZIRCONIUM 有权
标题翻译：生产金属锆的方法
公开(公告)号：US20110108434A1
公开(公告)日：2011-05-12
申请号：US13001870
申请日：2009-06-29
申请人： Reiko Fujita , Koji Mizuguchi , Hitoshi Nakamura , Kouki Fuse , Mitsuru Kawamoto , Masaru Ito
发明人： Reiko Fujita , Koji Mizuguchi , Hitoshi Nakamura , Kouki Fuse , Mitsuru Kawamoto , Masaru Ito
IPC分类号： C25C3/26
CPC分类号： C25C3/26 , C22B34/1222 , C22B34/129 , C22B34/14 , Y02P10/23
摘要： An object of the present invention is to provide a method of producing metal zirconium, the method having a fewer steps and a smaller amount of secondary wastes generated, wherein the metal zirconium is obtained from a zirconium compound containing hafnium. A method of producing metal zirconium according to the present invention includes: a separation step of separating a hafnium oxychloride from a first substance containing a zirconium oxychloride and a hafnium oxychloride to obtain a second substance having a higher content of the zirconium oxychloride; a calcination step of calcining the second substance to obtain a third substance containing at least any of a zirconium oxychloride and a zirconium oxide; and a direct reduction step of holding the third substance in a molten salt with the third substance brought into contact with a cathode and applying a voltage between the cathode and an anode to directly reduce the third substance to obtain metal zirconium.
摘要翻译：本发明的目的是提供一种生产金属锆的方法，该方法具有较少的步骤和较少量的二次废弃物，其中金属锆由含有铪的锆化合物获得。根据本发明的金属锆的制造方法包括：从含有氯氧化锆和氯化铪的第一物质中分离氯氧化铪的分离工序，得到氯氧化锆含量较高的第二物质; 煅烧第二物质以获得含有三氯氧化锆和氧化锆中的至少一种的第三物质的煅烧步骤; 以及将第三物质保持在与第一物质接触的第三物质与阴极接触并在阴极和阳极之间施加电压以直接还原第三物质以获得金属锆的直接还原步骤。

5. 发明授权

US08221609B2 Process for producing rare metal and production system thereof 有权
标题翻译：生产稀土金属的方法及其生产系统
公开(公告)号：US08221609B2
公开(公告)日：2012-07-17
申请号：US12813002
申请日：2010-06-10
申请人： Reiko Fujita , Hitoshi Nakamura , Koji Mizuguchi , Shohei Kanamura , Takashi Omori , Kazuhiro Utsunomiya , Shunji Nomura
发明人： Reiko Fujita , Hitoshi Nakamura , Koji Mizuguchi , Shohei Kanamura , Takashi Omori , Kazuhiro Utsunomiya , Shunji Nomura
IPC分类号： C25C3/34 , C25C7/00 , C25B1/00 , C25B9/06 , C25C3/30 , C25B1/21
CPC分类号： C25C3/34 , C25C7/00
摘要： According to one embodiment, a process for producing rare metals includes the steps of: electrolyzing an electrolytic solution to extract a Re oxide at a cathode; recovering the Re oxide, and electrolyzing the Re oxide in a molten salt electrolyte to extract metallic Re; recovering a Nd containing residue solution; treating the Nd containing residue solution to produce Nd oxide; electrolyzing the Nd oxide in a molten salt electrolyte to extract metallic Nd; recovering a Dy containing residue solution; treating the Dy containing residue solution to produce Dy oxide; and electrolyzing the Dy oxide in a molten salt electrolyte to extract metallic Dy.
摘要翻译：根据一个实施方案，制备稀有金属的方法包括以下步骤：电解电解液以在阴极提取Re氧化物; 回收Re氧化物，并在熔融盐电解液中电解Re氧化物以提取金属Re; 回收含Nd残留溶液; 处理含Nd残留溶液以产生Nd氧化物; 电解熔融盐电解质中的Nd氧化物以提取金属Nd; 回收含Dy残渣溶液; 处理含Dy残渣溶液以生成Dy氧化物; 并在熔盐电解质中电解Dy氧化物以提取金属Dy。

6. 发明申请

US20130001096A1 PROCESS FOR PRODUCING RARE METAL 有权
标题翻译：生产稀有金属的工艺
公开(公告)号：US20130001096A1
公开(公告)日：2013-01-03
申请号：US13527826
申请日：2012-06-20
申请人： Koji MIZUGUCHI , Shohei Kanamura , Tetsuo Osato , Yuya Takahashi , Yumi Yaita , Yu Yamashita , Reiko Fujita , Takashi Omori , Takashi Yazawa
发明人： Koji MIZUGUCHI , Shohei Kanamura , Tetsuo Osato , Yuya Takahashi , Yumi Yaita , Yu Yamashita , Reiko Fujita , Takashi Omori , Takashi Yazawa
IPC分类号： C25C3/34 , C25C1/22
CPC分类号： C22B3/0005 , C22B3/42 , C22B3/46 , C22B59/00 , C22B61/00 , C25C3/34 , Y02P10/234
摘要： According to one embodiment, a process for producing rare metals includes the steps of: recovering a first-residue solution through a primary target metal extracted by leaching a mineral resource; extracting a perrhenic acid ion contained in the first-residue solution with at least one of an anion exchange resin and a first-organic solvent; back extracting the perrhenic acid ion contained in the anion exchange resin or the first-organic solvent to a first-eluant; and electrolyzing the back extracted first-eluant to collect a rhenium at a cathode.
摘要翻译：根据一个实施方案，制备稀有金属的方法包括以下步骤：通过浸出矿物资源提取的初级靶金属回收第一残留物溶液; 用阴离子交换树脂和第一有机溶剂中的至少一种提取第一残留物溶液中所含的高铼酸离子; 将阴离子交换树脂或第一有机溶剂中含有的高铼酸离子反萃取至第一洗脱剂; 并电解反萃取的第一洗脱液以在阴极收集铼。

7. 发明授权

US08888985B2 Process for producing rare metal 有权
标题翻译：稀土金属生产工艺
公开(公告)号：US08888985B2
公开(公告)日：2014-11-18
申请号：US13527826
申请日：2012-06-20
申请人： Koji Mizuguchi , Shohei Kanamura , Tetsuo Osato , Yuya Takahashi , Yumi Yaita , Yu Yamashita , Reiko Fujita , Takashi Omori , Takashi Yazawa
发明人： Koji Mizuguchi , Shohei Kanamura , Tetsuo Osato , Yuya Takahashi , Yumi Yaita , Yu Yamashita , Reiko Fujita , Takashi Omori , Takashi Yazawa
IPC分类号： C22B59/00 , C22B3/04 , C22B3/22 , C22B3/26 , C22B3/46 , C25C3/34 , C22B3/42 , C22B61/00
CPC分类号： C22B3/0005 , C22B3/42 , C22B3/46 , C22B59/00 , C22B61/00 , C25C3/34 , Y02P10/234
摘要： According to one embodiment, a process for producing rare metals includes the steps of: recovering a first-residue solution through a primary target metal extracted by leaching a mineral resource; extracting a perrhenic acid ion contained in the first-residue solution with at least one of an anion exchange resin and a first-organic solvent; back extracting the perrhenic acid ion contained in the anion exchange resin or the first-organic solvent to a first-eluant; and electrolyzing the back extracted first-eluant to collect a rhenium at a cathode.
摘要翻译：根据一个实施方案，制备稀有金属的方法包括以下步骤：通过浸出矿物资源提取的初级靶金属回收第一残留物溶液; 用阴离子交换树脂和第一有机溶剂中的至少一种提取第一残留物溶液中所含的高铼酸离子; 将阴离子交换树脂或第一有机溶剂中含有的高铼酸离子反萃取至第一洗脱剂; 并电解反萃取的第一洗脱液以在阴极收集铼。

8. 发明授权

US06299748B1 Method and apparatus of treating waste from nuclear fuel handling facility 有权
标题翻译：处理核燃料处理设备废物的方法和装置
公开(公告)号：US06299748B1
公开(公告)日：2001-10-09
申请号：US09393317
申请日：1999-09-10
申请人： Naruhito Kondo , Reiko Fujita
发明人： Naruhito Kondo , Reiko Fujita
IPC分类号： C25C122
CPC分类号： G21F9/30 , C22B60/0213 , G21C19/48 , Y02W30/884
摘要： A waste treatment apparatus treats radioactive contaminated waste from a nuclear fuel material handling facility to decontaminate the radioactive contaminated waste by using an electrolytic molten salt, and reuses the electrolytic molten salt so that any effluents are not produced. Radioactive contaminated waste (10) from a nuclear fuel material handling facility is subjected to electrolysis by a molten salt electrolysis unit (20) to decontaminate the waste (10). The used salt (16) used for decontaminating the waste (10) is filtered to separate nuclear fuel materials (19) from the used salt (16). The filtered salt (18) is reused by the molten salt electrolysis unit (20). The salt adhering to the decontaminated waste (12) is recovered by an evaporating unit (59), and the recovered salt (15) is reused by the molten salt electrolysis unit (20).
摘要翻译：废物处理装置用核燃料处理设备处理放射性污染废物，通过使用电解熔融盐对放射性污染废物进行净化，并重新使用电解熔融盐，使得不产生任何污水。来自核燃料处理设备的放射性污染废物（10）通过熔融盐电解装置（20）进行电解以净化废物（10）。用于净化废物（10）的用过的盐（16）被过滤以将核燃料材料（19）与使用的盐（16）分离。过滤的盐（18）由熔盐电解装置（20）重复使用。附着在去污废物（12）上的盐通过蒸发单元（59）回收，回收盐（15）由熔融盐电解单元（20）再利用。

9. 发明授权

US06736951B2 Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same 有权
标题翻译：处理核燃料处理设备废物的方法及其执行方法
公开(公告)号：US06736951B2
公开(公告)日：2004-05-18
申请号：US09940932
申请日：2001-08-29
申请人： Naruhito Kondo , Reiko Fujita
发明人： Naruhito Kondo , Reiko Fujita
IPC分类号： C25C122
CPC分类号： G21F9/30 , C22B60/0213 , G21C19/48 , Y02W30/884
摘要： A waste treatment apparatus treats radioactive contaminated waste from a nuclear fuel material handling facility to decontaminate the radioactive contaminated waste by using an electrolytic molten salt, and reuses the electrolytic molten salt so that any effluents are not produced. Radioactive contaminated waste (10) from a nuclear fuel material handling facility is subjected to electrolysis by a molten salt electrolysis unit (20) to decontaminate the waste (10). The used salt (16) used for decontaminating the waste (10) is filtered to separate nuclear fuel materials (19) from the used salt (16). The filtered salt (18) is reused by the molten salt electrolysis unit (20). The salt adhering to the decontaminated waste (12) is recovered by an evaporating unit (59), and the recovered salt (15) is reused by the molten salt electrolysis unit (20).
摘要翻译：废物处理装置用核燃料处理设备处理放射性污染废物，通过使用电解熔融盐对放射性污染废物进行净化，并重新使用电解熔融盐，使得不产生任何污水。来自核燃料处理设备的放射性污染废物（10）通过熔融盐电解装置（20）进行电解以净化废物（10）。用于净化废物（10）的用过的盐（16）被过滤以将核燃料材料（19）与使用的盐（16）分离。过滤的盐（18）由熔盐电解装置（20）重复使用。附着在去污废物（12）上的盐通过蒸发单元（59）回收，回收盐（15）由熔融盐电解单元（20）再利用。

10. 发明授权

US6156183A Method of processing spent reactor fuel with magnesium alloy cladding 失效
标题翻译：用镁合金包层处理废反应堆燃料的方法
公开(公告)号：US6156183A
公开(公告)日：2000-12-05
申请号：US174591
申请日：1998-10-19
申请人： Naruhito Kondo , Kenichi Matsumaru , Reiko Fujita , Makoto Fujie
发明人： Naruhito Kondo , Kenichi Matsumaru , Reiko Fujita , Makoto Fujie
IPC分类号： G21C19/44 , C25C3/34 , G21C19/48 , C25C1/22
CPC分类号： C25C3/34 , G21C19/48 , Y02W30/884
摘要： A spent reactor fuel processing method is provided for recovering at least any one of metallic nuclear fuel materials, in which the reactor fuel is composed by covering the metallic nuclear fuel material with a cladding tube made of alloy and having a melting point lower than that of the metallic nuclear fuel material and end plugs made of alloy are mounted to both ends thereof. The processing method comprises a cladding tube smelting separation process, a molten salt electrorefining process and a salt evaporation separation process for recovering metallic uranium, uranium and plutonium, or uranium, plutonium and transuranium elements.
摘要翻译：提供了一种废反应堆燃料处理方法，用于回收金属核燃料材料中的至少一种，其中反应堆燃料由用合金制成的熔覆层覆盖金属核燃料材料构成，熔点低于金属核燃料材料和由合金制成的端塞安装在其两端。该处理方法包括熔覆熔炼分离工艺，熔盐电解精炼工艺和用于回收金属铀，铀和钚，或铀，钚和铀元素的盐蒸发分离过程。

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