公开(公告)号：US09721690B2

公开(公告)日：2017-08-01

申请号：US14761357

申请日：2014-01-16

Applicant: ALD VACUUM TECHNOLOGIES GMBH

Inventor： Henrik Franz ,  Karl-Heinz Grosse ,  Markus Holz ,  Michael Protzmann

IPC: F27B14/00 ,  G21F9/30 ,  F27B14/04 ,  F27B14/08 ,  G21F9/00 ,  G21D1/00

CPC classification number: G21F9/308 ,  F27B14/04 ,  F27B14/08 ,  F27B2014/0831 ,  G21D1/003 ,  G21F9/008

Abstract: A mobile melting device for consolidating contaminated scrap and to a corresponding method. The melting device has a crucible chamber and a crucible base. The crucible is arranged on the crucible base during operation, and the crucible base and the crucible chamber together form a gas-tight furnace housing. It is thus possible to carry out the method in a vacuum or under protective gas such that even a reactive material can be consolidated. The melting device can be assembled and disassembled with little effort.

公开(公告)号：US09704609B2

公开(公告)日：2017-07-11

申请号：US13984334

申请日：2011-02-15

Applicant: Gen-ichi Katagiri

Inventor： Gen-ichi Katagiri

IPC: H01L21/00 ,  C23C16/00 ,  G21F9/30 ,  G21F9/32 ,  H01J37/32 ,  H05H1/46

CPC classification number: G21F9/30 ,  G21F9/308 ,  G21F9/32 ,  H01J37/3211 ,  H05H1/46 ,  H05H2001/4667

Abstract: Provided is an ion exchange resin volume reduction apparatus in which the ignition of plasma is facilitated and the plasma is prevented from extinguishing. A volume reduction apparatus according to aspects of the present invention includes a stage carrying thereon a resin to be treated, a CCP power source, and an ICP power source. The volume reduction apparatus according to a certain aspect of the present invention is provided with a supply mechanism, and the CCP power source continues operating when the resin to be treated is supplied in a depressurized state to a vacuum vessel. In the volume reduction apparatus according to a certain aspect of the present invention, the CCP power source continues operating when a gas condition under which gas is supplied into the vacuum vessel is changed.

公开(公告)号：US20140044624A1

公开(公告)日：2014-02-13

申请号：US14113129

申请日：2012-04-23

Applicant: Nicolas Ghirelli ,  Pierre Trabuc ,  Olivier Gastaldi ,  Pascal Lejay ,  Joel Balay ,  Abdellali Hadj-Azzem

Inventor： Nicolas Ghirelli ,  Pierre Trabuc ,  Olivier Gastaldi ,  Pascal Lejay ,  Joel Balay ,  Abdellali Hadj-Azzem

IPC: G21F9/30 ,  G21F9/00

CPC classification number: G21F9/308 ,  G21B1/115 ,  G21F9/007 ,  G21F9/02 ,  G21F9/28 ,  G21F9/30

Abstract: The invention relates to a detritiation device comprising i) a furnace (1) for melting tritiated waste, said furnace comprising a hearth for receiving tritiated waste and a bubbling device for introducing a hydrogenated bubbling gas into the hearth during the melting and treatment of the tritiated waste in the furnace (1), and ii) a catalytic reactor with a quadrupole membrane (2) for treating the gas resulting from the melting and treatment of the tritiated waste in the furnace (1), said reactor comprising a membrane (20) for separating two flows of gas, the membrane (20) being permeable to the hydrogen isotopes. The invention also relates to an associated detritiation method.

Abstract translation: 本发明涉及一种除渣装置，包括：i）用于熔化氚化废物的炉子（1），所述炉子包括用于接收氚化废物的炉膛和用于在熔融和处理氚化废物的过程中将氢化鼓泡气体引入炉膛的鼓泡装置 在炉（1）中的废物，和ii）具有四极膜（2）的催化反应器，用于处理由熔融和处理炉（1）中的氚化废物产生的气体，所述反应器包括膜（20） 为了分离两个气体流，膜（20）对氢同位素是可渗透的。 本发明还涉及相关的脱粒方法。

公开(公告)号：US08506786B2

公开(公告)日：2013-08-13

申请号：US12763512

申请日：2010-04-20

Applicant: Joon-Bo Shim ,  Do-Hee Ahn ,  Seung-Woo Paek ,  Si-Hyung Kim ,  Sang-Woon Kwon ,  Kwang-Rag Kim ,  Han-Soo Lee

Inventor： Joon-Bo Shim ,  Do-Hee Ahn ,  Seung-Woo Paek ,  Si-Hyung Kim ,  Sang-Woon Kwon ,  Kwang-Rag Kim ,  Han-Soo Lee

IPC: C25C3/34 ,  G21C19/48

CPC classification number: C25C3/34 ,  C25C7/025 ,  G21C19/48 ,  G21F9/308 ,  Y02W30/884

Abstract: A method for recovery of residual actinide element from chloride molten salts that are formed after electro-refining and/or electro-winning of a spent nuclear fuel and include actinide elements and rare-earth elements is provided. The method comprises conducting electrolysis using a liquid cadmium cathode (LCC) in the chloride molten salt that is formed after electro-refining and/or electro-winning of a spent nuclear fuel and contains rare-earth elements and actinide elements; electro-depositing the actinide elements contained in the chloride molten salt on the LCC in order to reduce a concentration of the actinide elements; and adding a CdCl2 oxidant to the chloride molten salt containing the LCC-metal alloy in order to oxidize the rare-earth elements co-deposited on the LCC, thereby forming the rare-earth chlorides in the chloride molten salt.

Abstract translation: 提供了一种从废核燃料的电解和/或电击中形成的氯化物熔融盐中残留的锕系元素回收方法，包括锕系元素和稀土元素。 该方法包括使用在电解精炼和/或电核燃料中形成的含有稀土元素和锕系元素的氯化物熔盐中的液体镉阴极（LCC）进行电解; 将包含在氯化物熔融盐中的锕系元素电沉积在LCC上以降低锕系元素的浓度; 并向含有LCC-金属合金的氯化物熔盐中加入CdCl 2氧化剂，以便氧化共沉淀在LCC上的稀土元素，从而在氯化物熔融盐中形成稀土氯化物。

公开(公告)号：US20110017601A1

公开(公告)日：2011-01-27

申请号：US12763512

申请日：2010-04-20

Applicant: Joon-Bo Shim ,  Do-Hee Ahn ,  Seung-Woo Paek ,  Si-Hyung Kim ,  Sang-Woon Kwon ,  Kwang-Rag Kim ,  Han-Soo Lee

Inventor： Joon-Bo Shim ,  Do-Hee Ahn ,  Seung-Woo Paek ,  Si-Hyung Kim ,  Sang-Woon Kwon ,  Kwang-Rag Kim ,  Han-Soo Lee

IPC: C25C3/34

CPC classification number: C25C3/34 ,  C25C7/025 ,  G21C19/48 ,  G21F9/308 ,  Y02W30/884

Abstract: A method for recovery of residual actinide element from chloride molten salts that are formed after electro-refining and/or electro-winning of a spent nuclear fuel and include actinide elements and rare-earth elements is provided. The method comprises conducting electrolysis using a liquid cadmium cathode (LCC) in the chloride molten salt that is formed after electro-refining and/or electro-winning of a spent nuclear fuel and contains rare-earth elements and actinide elements; electro-depositing the actinide elements contained in the chloride molten salt on the LCC in order to reduce a concentration of the actinide elements; and adding a CdCl2 oxidant to the chloride molten salt containing the LCC-metal alloy in order to oxidize the rare-earth elements co-deposited on the LCC, thereby forming the rare-earth chlorides in the chloride molten salt.

Abstract translation: 提供了一种从废核燃料的电解和/或电击中形成的氯化物熔融盐中残留的锕系元素回收方法，包括锕系元素和稀土元素。 该方法包括使用在电解精炼和/或电核燃料中形成的含有稀土元素和锕系元素的氯化物熔盐中的液体镉阴极（LCC）进行电解; 将包含在氯化物熔融盐中的锕系元素电沉积在LCC上以降低锕系元素的浓度; 并向含有LCC-金属合金的氯化物熔盐中加入CdCl 2氧化剂，以便氧化共沉淀在LCC上的稀土元素，从而在氯化物熔融盐中形成稀土氯化物。

公开(公告)号：US20070039487A1

公开(公告)日：2007-02-22

申请号：US11205099

申请日：2005-08-17

Applicant: Tsung-Min Hung ,  Ping-Chun Kuo ,  Maw-Suey Kuo ,  Chin-Ching Tzeng ,  Deng-Lian Lin

Inventor： Tsung-Min Hung ,  Ping-Chun Kuo ,  Maw-Suey Kuo ,  Chin-Ching Tzeng ,  Deng-Lian Lin

IPC: A23L3/18

CPC classification number: G21F9/32 ,  G21F9/308

Abstract: The present invention continuously transports and cools down plasma lava with no gas explosion under an indirect cooling; comprises fewer rotating parts for transportation; prevents radioactive pollutants from escaping out under an air-locked environment; and, avoids motor of transport caravan operating under high temperature, where the present invention can be applied to a plasma melting process for radioactive material.

Abstract translation: 本发明在间接冷却下连续输送和冷却等离子体熔岩，无气体爆炸; 包括较少用于运输的旋转部件; 防止放射性污染物在空气环境下逸出; 并且避免了在高温下运行的运输商队的动力，其中本发明可以应用于放射性物质的等离子体熔化过程。

公开(公告)号：US4895678A

公开(公告)日：1990-01-23

申请号：US363305

申请日：1989-06-08

Applicant: Katsuyuki Ohtsuka ,  Jin Ohuchi ,  Hideaki Tamai

Inventor： Katsuyuki Ohtsuka ,  Jin Ohuchi ,  Hideaki Tamai

IPC: G21F9/06 ,  G21F9/14 ,  G21F9/30

CPC classification number: G21F9/30 ,  G21F9/14 ,  G21F9/308 ,  Y10S159/12

Abstract: A method for thermal decomposition treatment of a radioactive waste uses an apparatus comprising a container for holding molten matter of a radioactive waste containing a sodium compound, a pair of electrodes contacting the molten matter, and a power source for applying voltage between the electrodes while changing the polarity thereof every several tens of seconds. In this apparatus, the molten matter can be heated in the container by Joule heat, which is evolved by electric current directly flowed through the molten matter, so that the sodium compound contained in the radioactive waste can be decomposed, vaporized and removed to recover a stabilized radioactive solid as a residue in the container.

Abstract translation: 放射性废物的热分解处理方法使用的装置包括容纳含有钠化合物的放射性废物的熔融物质的容器，与熔融物接触的一对电极以及在电极之间施加电压的电源，同时改变 其极性每隔几十秒。 在该装置中，可以通过焦耳热在容器中加热熔融物质，焦耳热通过直接流过熔融物质的电流放出，使得放射性废物中所含的钠化合物能够分解，蒸发并除去 稳定的放射性固体作为容器中的残留物。

公开(公告)号：US20230245794A1

公开(公告)日：2023-08-03

申请号：US17591167

申请日：2022-02-02

Applicant: CURIO SOLUTIONS LLC

Inventor： YECHEZKEL MOSKOWITZ ,  YEHUDAH MOSKOWITZ ,  VIK SINGH

IPC: G21C19/46 ,  G21F9/00 ,  G21F9/30

CPC classification number: G21C19/46 ,  G21F9/007 ,  G21F9/308

Abstract: A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce U3O8. A fluorination vessel is coupled to the decladding vessel to remove hexafluorides from the U3O8 produced by the decladding vessel. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.

公开(公告)号：US09234258B2

公开(公告)日：2016-01-12

申请号：US14182788

申请日：2014-02-18

Applicant: United States Department of Energy

Inventor： Harmon M. Tunison

IPC: C22B9/10 ,  C22B13/02 ,  G21F9/30 ,  C22B13/06

CPC classification number: C22B13/06 ,  C22B9/10 ,  C22B9/103 ,  C22B9/106 ,  C22B13/02 ,  C22B13/025 ,  G21F9/308

Abstract: Disclosed is an exemplary method of purifying lead which includes the steps of placing lead and a fluoride salt blend in a container; forming a first fluid of molten lead at a first temperature; forming a second fluid of the molten fluoride salt blend at a second temperature higher than the first temperature; mixing the first fluid and the second fluid together; separating the two fluids; solidifying the molten fluoride salt blend at a temperature above a melting point of the lead; and removing the molten lead from the container. In certain exemplary methods the molten lead is removed from the container by decanting. In still other exemplary methods the molten salt blend is a Lewis base fluoride eutectic salt blend, and in yet other exemplary methods the molten salt blend contains sodium fluoride, lithium fluoride, and potassium fluoride.

Abstract translation: 公开了一种纯化铅的示例性方法，其包括将铅和氟化物盐混合物放置在容器中的步骤; 在第一温度下形成熔融铅的第一流体; 在高于第一温度的第二温度下形成熔融氟化物盐混合物的第二流体; 将第一流体和第二流体混合在一起; 分离两种流体; 在高于熔点的温度下固化熔融氟化物盐混合物; 并从容器中取出熔融铅。 在某些示例性方法中，通过倾析将熔融铅从容器中取出。 在其它示例性方法中，熔融盐共混物是路易斯碱氟化物共晶盐共混物，而在其它示例性方法中，熔融盐共混物含有氟化钠，氟化锂和氟化钾。

公开(公告)号：US08829261B2

公开(公告)日：2014-09-09

申请号：US13871037

申请日：2013-04-26

Applicant: Kepco Nuclear Fuel Co., Ltd.

Inventor： Suk Ju Cho ,  Young Bae Lee ,  Jeung Gun Seol ,  Yong Jae Kim ,  Wook Jin Han ,  Jae Bong Ryu ,  Hyun Gyu Kang

IPC: G21F9/16 ,  G21F9/30

CPC classification number: G21F9/308 ,  G21F9/30 ,  G21F9/301 ,  G21F9/34 ,  Y10S588/901

Abstract: Disclosed herein is a method of treating radioactive metal waste using melt decontamination, wherein radioactive metal waste, which is generated from nuclear fuel processing facilities or nuclear fuel production facilities, and which cannot be easily treated by surface decontamination because it has a complicated geometric shape, and the surface contamination of which cannot be measured, can be treated by melt decontamination. The method is advantageous in that radioactive metal waste, which cannot be treated by conventional surface decontamination, can be treated, so that radioactive metal waste can be recycled, thereby obtaining economic profits, and further in that a large storage space necessary for cutting and then storing radioactive metal waste is not required, and in that excessive manpower and cost are not required.

Abstract translation: 本文公开了一种使用熔融去污处理放射性金属废物的方法，其中由核燃料处理设施或核燃料生产设备产生的放射性金属废物，由于其具有复杂的几何形状而不能容易地通过表面去污处理， 并且其表面污染物无法测量，可以通过熔体去污处理。 该方法的优点在于，可以处理不能通过常规表面去污处理的放射性金属废物，从而可以回收放射性金属废物，从而获得经济利益，进一步地，切割所需的大量储存空间 不需要储存放射性金属废物，因此不需要过多的人力和费用。