公开(公告)号：JP2005221439A

公开(公告)日：2005-08-18

申请号：JP2004031314

申请日：2004-02-06

Applicant: Japan Nuclear Cycle Development Inst States Of Projects ,  National Institute For Materials Science ,  Nagaaki Satou ,  修彰 佐藤 ,  核燃料サイクル開発機構 ,  独立行政法人物質・材料研究機構

Inventor： SATO SOICHI ,  SATOU NAGAAKI ,  OBARA KENJI

IPC: G21C19/44

CPC classification number: Y02W30/882

Abstract: PROBLEM TO BE SOLVED: To make it possible to separate fuel substances from other nuclear fission products without dissolving the substances as they remain oxides. SOLUTION: This method includes (1) a pulverization process for pulverizing fuel elements by heating and oxidizing spent fuel, (2) a selective sulfurization process for reducing the fuel substances and selectively sulfurizing nuclear fission products into sulfide or oxysulfide by heating the pulverulent bodies obtained in the pulverization process in an atmosphere containing a sulfurizer and (3) a magnetic separation process for collecting compounds of fuel elements and those of some nuclear fission product elements by suspending the compounds of the fuel elements and the nuclear fission product elements obtained in the previous process in a fluid and passing them through a magnetic separator and additionally separating them on the basis of the difference in their magnetic susceptibilities. COPYRIGHT: (C)2005,JPO&NCIPI

Abstract translation: 要解决的问题：为了使燃料物质与其他核裂变产物分离而不会在物质保留氧化物时溶解，可能会有可能。 解决方案：该方法包括（1）通过加热和氧化废燃料来粉碎燃料元件的粉碎过程，（2）选择性硫化方法，用于减少燃料物质，并通过加热将核裂变产物选择性硫化成硫化物或硫化硫 在含有硫化剂的气氛中在粉碎过程中获得的粉末体和（3）通过悬浮获得的燃料元素和核裂变产物元素的化合物来收集燃料元素和某些核裂变产物元素化合物的磁分离方法 在先前的流程中，并将其通过磁选机，并根据它们的磁化率差异另外分离它们。 版权所有（C）2005，JPO＆NCIPI

公开(公告)号：JP2005201886A

公开(公告)日：2005-07-28

申请号：JP2004169557

申请日：2004-06-08

Applicant: Korea Atom Energ Res Inst ,  Korea Hydro & Nuclear Power Co Ltd ,  韓国原子力研究所 ,  韓国水力原子力株式会社

Inventor： IN-KYU CHOI ,  YAN-FAN CHO ,  JEI-WON YON ,  WON-HO KIM ,  TEKU-JIN KIM

IPC: G01N27/416 ,  G01N27/26 ,  G21C19/44

CPC classification number: G21C19/44 ,  G21C19/48 ,  Y02W30/882 ,  Y02W30/884

Abstract: PROBLEM TO BE SOLVED: To provide a real-time measuring method for a uranium oxide reduction process by metal lithium.
SOLUTION: In this measuring method for measuring a conversion rate of metal uranium in a process for manufacturing metal uranium by a reaction of uranium oxide (UO
x , x≤3) with metal lithium in the presence of a high-temperature molten salt, a measuring instrument is constituted of a constant potential/constant current power source, and an oxidation electrode and a reduction electrode in a reaction vessel, and the conversion rate of the metal uranium is measured using an electrochemical analytical method based on an oxidation reaction by oxide ion dissociated from the lithium oxide obtained as a by-product, and based on a reduction reaction by lithium ion. An progress situation in the reduction process is grasped accurately in real time, and a quick and simple measuring technique is provided, since the oxidation electrode and the reduction electrode are connected to the constant potential/constant current power source to measure directly a conversion rate of the uranium oxide reduction reaction in the high-temperature molten salt.
COPYRIGHT: (C)2005,JPO&NCIPI

Abstract translation: 要解决的问题：提供金属锂对氧化铀还原过程的实时测量方法。 解决方案：在该测量方法中，通过氧化铀（UO x ，x≤3）与金属锂的反应来制造金属铀的方法中的金属铀的转化率 存在高温熔盐，测量仪器由恒电位/恒流电源，反应容器中的氧化电极和还原电极构成，并且使用电化学法测量金属铀的转化率 基于由作为副产物获得的氧化锂分解的氧化物离子的氧化反应的分析方法，以及通过锂离子的还原反应。 减少处理的进展情况被实时准确地掌握，并且提供了一种快速简单的测量技术，因为氧化电极和还原电极连接到恒定电位/恒流电源，以直接测量转换速率 高温熔盐中的氧化铀还原反应。 版权所有（C）2005，JPO＆NCIPI

公开(公告)号：JP3510985B2

公开(公告)日：2004-03-29

申请号：JP10329399

申请日：1999-04-09

Applicant: 財団法人電力中央研究所

Inventor： 正 井上 ,  茂行 和田 ,  保男 土江 ,  政利 飯塚

IPC: G21C19/34 ,  G21C19/44 ,  G21F9/30

CPC classification number: Y02W30/881 ,  Y02W30/882

公开(公告)号：JP2004028808A

公开(公告)日：2004-01-29

申请号：JP2002185962

申请日：2002-06-26

Applicant: Inst Of Research & Innovation ,  Toshiba Corp ,  株式会社東芝 ,  財団法人産業創造研究所

Inventor： YASUIKE YOSHIYUKI ,  SUZUKI KAZUNORI ,  MIZUGUCHI KOJI ,  ARIE KAZUO ,  IKEDA YASUHISA

IPC: G21C19/44

CPC classification number: Y02W30/882

Abstract: PROBLEM TO BE SOLVED: To enhance separation efficiency for separating an impurity from a nuclear material, and to enhance a reprocessing speed. SOLUTION: A fuel rod is heat-treated under chlorine gas to chlorinate a spent fuel and a sheathing material (first chlorination processing). A solid component provided in the first chlorination processing is heat-treated under chlorine gas containing a reductant (second chlorination processing). A gas component obtained in the second chlorination processing is recovered as a solid component (gas component recovery), and the solid component is heat-treated under the presence of mixture gas comprising chlorine gas and oxygen gas (oxidation processing). The solid component provided in the second chlorination processing is heat-treated under inert gas (FP separation processing). A solid component obtained in the oxidation processing, and a solid component obtained in the FP separation processing are dissolved into a molten salt to electrolyze the molten salt (MOX electrolyzing processing). COPYRIGHT: (C)2004,JPO

公开(公告)号：JP2003344578A

公开(公告)日：2003-12-03

申请号：JP2002152371

申请日：2002-05-27

Applicant: Toshiba Corp ,  株式会社東芝

Inventor： FUJITA REIKO ,  NAKAMURA HITOSHI ,  MIZUGUCHI KOJI ,  HIROSE EMIKO ,  SHIBANO TAKAYUKI ,  NATSUI KAZUJI ,  MATSUMOTO KOICHI ,  HAYASHIDA YOSHIHISA

IPC: G21C19/44 ,  C22B34/14 ,  C25C3/26 ,  C25C3/34

CPC classification number: Y02P10/212 ,  Y02W30/882

Abstract: PROBLEM TO BE SOLVED: To recover uranium and transuranium elements from a cladding tube and a channel box contaminated with uranium and transuranium elements and recover zirconium at a high purity. SOLUTION: The cladding tube and cladding hulls 25 of the channel box contaminated with uranium (U) and transuranium elements (TRU) are contained in an anode basket 20 and dipped in a molten salt. KCl-LiCl-ZrCl 2 having a low UO 2 solubility is used as the molten salt. Fused-salt electrolysis is executed in an electrolytic cell 18 by using iron or molybdenum as a cathode 19. Nb, Mo and Co which are contamination nuclides are recovered at the first cathode. When Zr starts depositing, the first cathode is replaced with the second cathode to deposit and recover metallic Zr at the second cathode. In the case of metallic uranium and transuranium elements adhering, they remain in the molten salt, and oxide settles as precipitate 28 on a bottom plate of the electrolytic cell 18 and is recovered. COPYRIGHT: (C)2004,JPO

Abstract translation: 要解决的问题：从铀和铀元素污染的包层管和通道箱中回收铀和铀元素，并以高纯度回收锆。 解决方案：被铀（U）和铀元素（TRU）污染的通道箱的包层管和包壳25被包含在阳极筐20中并浸入熔融盐中。 使用具有低UO 2 溶解度的KCl-LiCl-ZrCl 2 作为熔融盐。 通过使用铁或钼作为阴极19在电解槽18中进行熔盐电解。在第一阴极回收作为污染核素的Nb，Mo和Co。 当Zr开始沉积时，第一阴极被第二阴极替代，以在第二阴极沉积和回收金属Zr。 在金属铀和超铀元素附着的情况下，它们保留在熔融盐中，并且氧化物作为沉淀物28沉降在电解槽18的底板上并被回收。 版权所有（C）2004，JPO

公开(公告)号：JP2002371347A

公开(公告)日：2002-12-26

申请号：JP2001179994

申请日：2001-06-14

Applicant: Nkk Corp ,  日本鋼管株式会社

Inventor： YANAGI EIICHI ,  SUENAGA HIROYOSHI ,  URABE NAMIO

IPC: G21C19/44 ,  C23C4/08 ,  C23C4/12 ,  C23C30/00 ,  F27B14/10 ,  F27D1/00 ,  G21F9/30

CPC classification number: Y02W30/882

Abstract: PROBLEM TO BE SOLVED: To improve corrosion resistance of a forced cooling type induction- heating crucible made from copper, used for reprocessing of a spent nuclear fuel. SOLUTION: The method for preventing corrosion of a forced cooling type induction-heating crucible made from copper, used for dissolving a halogen compound, is characterized by arranging an anticorrosion layer of a metal with thermal conductivity of 5 W/m.K or higher, on the surface of the above crucible. The metal is preferably a Ni-based high alloy. The anticorrosion layer preferably comprises three layers consisting of a layer closest to the surface of the crucible having void fraction of 7.5%, a layer having void fraction of 8.5% or higher thereon, and a layer having void fraction of 5.5% or lower further thereon.

Abstract translation: 要解决的问题：提高用于废核燃料后处理的由铜制成的强制冷却型感应加热坩埚的耐腐蚀性。 解决方案：用于防止用于溶解卤素化合物的由铜制成的强制冷却型感应加热坩埚的腐蚀的方法的特征在于将热导率为5W / m·K以上的金属的防腐层配置在 上述坩埚的表面。 金属优选为Ni系高合金。 防腐层优选包括三层，其最靠近坩埚表面的空隙率为7.5％，空隙率为8.5％以上的层和其上空隙率为5.5％以下的层 。

公开(公告)号：JP2000075086A

公开(公告)日：2000-03-14

申请号：JP24283598

申请日：1998-08-28

Applicant: Hitachi Ltd ,  株式会社日立製作所

Inventor： SASAHIRA AKIRA ,  FUKAZAWA TETSUO ,  YOKOI HIROTO ,  KAWAMURA FUMIO

IPC: G21C19/44

CPC classification number: Y02W30/882

Abstract: PROBLEM TO BE SOLVED: To increase the dissolution speed of fuel, and to quickly perform collection by using metal being easily deposited from uranium oxide as an anode, by dissolving the metal by electrolysis, and by dissolving the fuel due to the action of a metal ion that has been dissolved. SOLUTION: A reprocessing device is composed of an electrolytic tank 1, fused salt 2, a cathode 3, an anode 4 being manufactured by metal that is not easily dissolved by uranium oxide, a reference electrode 5, an electrolysis device 6, and spent oxide fuel 7. The spent oxide fuel 7 is loaded to the anode 4, and is dipped into the fused salt 2. According to the potential difference between the reference electrode 5 and the anode 4, voltage is applied to the cathode 3 and the anode 4, and an application voltage is increased up to potential where Au is oxidized and dissolved. The fuel being brought into contact with the anode 4 out of the fuel being loaded on the anode 4 is oxidized at the anode 4, and uranium is dissolved. Since An Au ion in the fused salt 2 oxidizes the fuel for dissolving the uranium, the uranium is also dissolved from the fuel that is not in contact with the anode 4. The deposited uranium is collected at the cathode 3, and plutonium is collected from the anode 4.

Abstract translation: 要解决的问题：为了提高燃料的溶解速度，并且通过使用容易从氧化铀作为阳极沉积的金属，通过电解溶解金属和通过金属的作用溶解燃料来快速地进行收集 已经溶解的离子。 解决方案：再生处理装置由电解槽1，熔盐2，阴极3，阳极4由不易被氧化铀溶解的金属制成，参比电极5，电解装置6和废氧化物 燃料7.将废弃的氧化物燃料7装载到阳极4，并浸入熔融盐2.根据参考电极5和阳极4之间的电位差，向阴极3和阳极4施加电压 ，并且施加电压增加到Au被氧化和溶解的电位。 与负载在负极4上的燃料中的阳极4接触的燃料在阳极4处被氧化，并且铀被溶解。 由于熔融盐2中的Au离子氧化用于溶解铀的燃料，铀也从与阳极4不接触的燃料中溶解。沉积的铀在阴极3处收集，钚从 阳极4。

公开(公告)号：JPS58181730A

公开(公告)日：1983-10-24

申请号：JP6277382

申请日：1982-04-14

Applicant: Unitika Ltd

Inventor： ECHIGO YOSHIAKI ,  ISHIKURA TADASHI

IPC: C01G43/00 ,  C22B60/02 ,  G21C19/44 ,  G21C19/46

CPC classification number: Y02W30/882 ,  Y02W30/883

Abstract: PURPOSE: To recover uranium very efficiently from an acidic aqueous soln. by bringing the soln. into contact with an aminomethylenephosphonic acid deriv. to form a water insoluble solid complex contg. uranium.
CONSTITUTION: An acidic aqueous soln. contg. uranium is brought into contact with an aminomethylenephosphonic acid deriv. to form a water insoluble solid complex consisting of said deriv. and uranium. The complex is separated by filtration, and an aqueous alkali soln. is added to the separated complex to recover the uranium as hydroxide. The preferred aminomethylenephosphonic acid deriv. is a compound represented by general formula I , II or III, wherein each of R
1 WR
12 is H, 1W50C aliphatic or aromatic hydrocarbon group which may have halogen, carboxyl, hydroxyl, thiol, amino, phosphonic acid, aminomethylenephosphonic acid or other group substituting a part of the H atoms, and each of n and m is an integer of 1W20.
COPYRIGHT: (C)1983,JPO&Japio

Abstract translation: 目的：从酸性水溶液中非常有效地回收铀。 通过把soln。 与氨基亚甲基膦酸衍生物接触。 形成水不溶性固体复合物 铀。 构成：酸性水溶胶。 对比 使铀与氨基亚甲基膦酸衍生物接触。 以形成由所述衍生物组成的水不溶性固体络合物。 和铀。 通过过滤分离复合物和碱性水溶液。 加入到分离的络合物中以回收铀作为氢氧化物。 优选的氨基亚甲基膦酸衍生物 是由通式I，II或III表示的化合物，其中R1-R12各自为H，可具有卤素，羧基，羟基，硫醇，氨基，膦酸，氨基亚甲基膦酸或其它的1-50C脂族或芳族烃基 组取代H原子的一部分，n和m分别为1-20的整数。

公开(公告)号：JP2018524574A

公开(公告)日：2018-08-30

申请号：JP2017564560

申请日：2016-06-02

Applicant: ジーイー−ヒタチ・ニュークリア・エナジー・アメリカズ・エルエルシー ,  GE−HITACHI NUCLEAR ENERGY AMERICAS, LLC

Inventor： ミラー,ゲイリー・エル ,  ケラー,キース・エイチ

IPC: C25C3/36 ,  C25C7/02 ,  C25C7/06 ,  G21C19/34 ,  G21C19/46 ,  G21C3/60

CPC classification number: C25D17/12 ,  C25C3/34 ,  C25C7/005 ,  C25C7/025 ,  C25C7/08 ,  C25D3/54 ,  G21C19/42 ,  G21C19/44 ,  G21C19/48 ,  G21C21/02 ,  G21F9/30 ,  Y02W30/882 ,  Y02W30/884

Abstract: 核燃料構造体を製作する方法が、陰極組立体内の金属酸化物を、金属酸化物の金属を陰極組立体の陰極板に析出させるように還元することと、析出した金属を伴う陰極板を処理して核燃料構造体を製造することと、を含みうる。陰極板は、導電性材料を含む上側ブレードと、上側ブレードに接続された下側ブレード部分と、電気的連続性をもたらしながら下側ブレード部分を上側ブレードに固定するように構成された接続構造体と、を含みうる。接続構造体は、下側ブレード部分を上側ブレードから取り外すために下側ブレード部分から接続解除されるように構成されうる。 【選択図】図2A

公开(公告)号：JP2017146270A

公开(公告)日：2017-08-24

申请号：JP2016030084

申请日：2016-02-19

Applicant: 日立GEニュークリア・エナジー株式会社

Inventor： 星野 国義 ,  深澤 哲生 ,  渡邊 伸二 ,  笹平 朗 ,  渡邉 大輔

IPC: G21C19/44

CPC classification number: Y02W30/882

Abstract: 【課題】被覆燃料粒子を再処理する際、機械的脱被覆によらないで被覆成分を除去し、飛散物による汚染や機器の損耗等を少なくするとともに、ウランを除染の対象とすることなく回収する。 【解決手段】使用済燃料の再処理をする方法であって、使用済の被覆粒子燃料の構成元素をフッ化する工程(S102)と、フッ化する工程で生成したフッ化物を冷却することによりウラン及びプルトニウムのフッ化物を他のガスから分離する工程(S103)と、を含む。 【選択図】図2