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公开(公告)号：WO2020123509A1
公开(公告)日：2020-06-18
申请号：PCT/US2019/065483
申请日：2019-12-10
Applicant: ALPHA TECH RESEARCH CORP.
Inventor： BENSON, John , MEMMOTT, Matthew , FARRAR, Kraig
Abstract: Some embodiments include a molten salt system comprising a reactor with a salt mixture. In some embodiments, the salt mixture includes uranium and a eutectic salt. The eutectic salt may include one or more of sodium fluoride, potassium fluoride, aluminum fluoride, zirconium fluoride, lithium fluoride, beryllium fluoride, rubidium fluoride, magnesium fluoride, calcium fluoride, sodium chloride, potassium chloride, aluminum chloride, zirconium chloride, lithium chloride, beryllium chloride, rubidium chloride, magnesium chloride, and calcium chloride. The eutectic salt may have a melting point less than about 800° C.
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公开(公告)号：WO2017106509A1
公开(公告)日：2017-06-22
申请号：PCT/US2016/066944
申请日：2016-12-15
Applicant: ELYSIUM INDUSTRIES LTD. , HANSON, Michael, E.
Abstract: A salt composition for use as a fuel in a nuclear reactor is provided. The salt composition can include carrier salts having mixtures of one or more chloride salts or one or more chloride salts and one or more fluoride salts and fuel salts including one or more chloride salts. The carrier salts can include alkali and/or alkaline earth cations, while the fuel salts can include actinide cations. The salt composition has a lower melting temperature, less corrosive redox properties, and allows proliferation- safe retention of actinides and concurrent removal of some fission products, as compared to other salts employed in molten salt reactors. Optionally, the salt composition can include one or more metal halides for further decreasing the melting point and/or increasing the boiling point of the composition, thereby increasing the range of the liquid phase of the salt composition.
Abstract translation: 提供了用作核反应堆中的燃料的盐组合物。 盐组合物可以包括具有一种或多种氯化物盐或一种或多种氯化物盐和一种或多种氟化物盐和燃料盐（包括一种或多种氯化物盐）的混合物的载体盐。 载体盐可以包括碱和/或碱土阳离子，而燃料盐可以包括act系阳离子。 与熔盐反应器中使用的其他盐相比，盐组合物具有更低的熔化温度，更少的腐蚀性氧化还原性质，并且允许增殖安全地保留act系元素并同时除去一些裂变产物。 任选地，盐组合物可以包含一种或多种金属卤化物，用于进一步降低组合物的熔点和/或增加组合物的沸点，由此增加盐组合物的液相范围。
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公开(公告)号：WO00058219A1
公开(公告)日：2000-10-05
申请号：PCT/US2000/008022
申请日：2000-03-27
CPC classification number: C01G43/01 , C01B7/191 , C01B9/08 , C01G43/025 , C01G43/06 , C01P2002/72 , C01P2006/80
Abstract: A method for producing uranium oxide includes combining uranium oxyfluoride and a solid oxidizing agent having a lower thermodynamic stability than the uranium oxide; heating the combination below the vapor point of the uranium oxyfluoride to sufficiently react the uranium oxyfluoride and the oxidizing agent to produce uranium oxide and a non-radioactive fluorine compound; and removing the fluorine compound.
Abstract translation: 一种生产氧化铀的方法包括将铀氧氟化物和具有比铀氧化物更低的热力学稳定性的固体氧化剂组合; 将低于氟氧化铀的蒸气点的组合加热以使氟氧化铀和氧化剂充分反应以产生铀氧化物和非放射性氟化合物; 并除去氟化合物。
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公开(公告)号：WO1995015921A1
公开(公告)日：1995-06-15
申请号：PCT/GB1994002670
申请日：1994-12-06
Applicant: BRITISH NUCLEAR FUELS PLC , JEAPES, Andrew, Philip , FIELDS, Mark , McGRADY, Gerard, Sean
Inventor： BRITISH NUCLEAR FUELS PLC
IPC: C01G43/06
CPC classification number: C01G43/063 , C01G56/006 , G21C19/48 , Y02W30/884
Abstract: A method of purifying a UF6 gas stream which comprises irradiating the UF6 gas stream with laser radiation in a vessel in order to selectively convert fluoride impurities in the gas stream to involatile products, removing the purified UF6 gas stream from the vessel and separately removing the impurities from the vessel.
Abstract translation: 一种净化UF6气流的方法，其包括在容器中用激光辐射照射UF6气流，以便将气流中的氟化物杂质选择性地转化为非挥发性产物，从容器中除去纯化的UF6气流，并分别除去杂质 从船只。
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公开(公告)号：WO2018221811A1
公开(公告)日：2018-12-06
申请号：PCT/KR2017/014802
申请日：2017-12-15
Applicant: 한전원자력연료 주식회사
Abstract: 본 발명은 기상반응을 통한 UF 6 heel의 처리방법 및 처리장치에 관한 것으로서, 구체적인 처리방법은 (1) UF 6 heel을 기화시키는 단계; (2) 상기 기화된 UF 6 가스를 이용하여 고상의 UO 2 F 2 를 생성하는 단계; (3) 상기 고상의 UO 2 F 2 와 부산(副産)가스를 분리하는 단계; 및 (4) 상기 부산가스 중 불화수소를 분리하는 단계;를 포함하고, 처리장치는 (1) UF 6 heel을 기화하기 위한 전용기화기, (2) 상기 기화기와 연결되어 기화기에서 생성된 UF 6 가스를 이용하여 UO 2 F 2 를 생성하는 반응기, (3) 상기 반응기와 연결되어 반응기에서 생성된 고상의 UO 2 F 2 를 부산가스와 분리하는 고ㆍ기상 분리기, (4) 상기 고ㆍ기상 분리기와 연결되어 고ㆍ기상 분리기에서 공급된 부산가스를 통과시켜 액체를 응축시키는 열교환기 및 (5) 상기 열교환기에서 응축된 불화수소 액체와 가스로 분리하는 액ㆍ기상 분리기;를 포함할 수 있다. 상기와 같은 본 발명에 따르면, UF 6 heel 처리를 통하여 UO 2 분말의 중간물질인 고상의 UO 2 F 2 를 제조함으로써 재변환 공정의 안정화와 UO 2 분말의 품질을 향상할 수 있으며, UF 6 heel을 0.5kg 미만으로 최소화하여 값비싼 방사성 폐기물의 처리비용도 줄이는 효과가 있다.
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Patent Agency Ranking6.发明申请UTILISATION D'UN COMPOSÉ KMgF3 POUR PIÉGER DES MÉTAUX PRÉSENTS SOUS FORME DE FLUORURES ET/OU D'OXYFLUORURES DANS UNE PHASE GAZEUSE OU LIQUIDE 审中-公开使用KMGF3化合物在气相或液相中的氟化物和/或氧化物形式中捕获金属
公开(公告)号：WO2012168420A1
公开(公告)日：2012-12-13
申请号：PCT/EP2012/060875
申请日：2012-06-08
Applicant: COMURHEX SOCIETE POUR LA CONVERSION DE L'URANIUM EN METAL ET HEXAFLUORURE , MOREL, Bertrand , LEITE, Lorraine , MOCH, Laurent , DEMOURGUES, Alain , CLARENC, Romain , TRESSAUD, Alain , DURAND, Etienne
Inventor： MOREL, Bertrand , LEITE, Lorraine , MOCH, Laurent , DEMOURGUES, Alain , CLARENC, Romain , TRESSAUD, Alain , DURAND, Etienne
CPC classification number: C22B60/0278 , B01D53/02 , B01D53/685 , B01D2251/306 , B01D2251/402 , B01J20/046 , B01J20/28004 , B01J20/28057 , B01J20/3028 , B01J20/3078 , B01J20/3085 , C01D3/02 , C01F5/28 , C01G43/063 , C01P2002/72 , C01P2002/82 , C01P2006/12 , C22B60/0213 , G21C19/46 , G21F9/04 , G21F9/06 , Y02C20/30 , Y02W30/883
Abstract: L'invention se rapporte à l'utilisation d'un composé de formule KMgF 3 pour piéger des métaux présents sous forme de fluorures et/ou d' oxyfluorures dans une phase gazeuse ou liquide. Elle se rapporte également à un composé de formule KMgF 3 qui présente une surface spécifique au moins égale à 30 m 2 /g et au plus égale à 150 m 2 /g ainsi qu'à ses procédés de préparation. L' invention trouve notamment application dans l'industrie nucléaire où elle peut avantageusement être mise à profit pour purifier l'hexafluorure d'uranium (UF 6 ) présent dans un flux gazeux ou liquide vis-à-vis des impuretés métalliques qui se trouvent également dans ce flux.
Abstract translation: 本发明涉及具有式KMgF 3的化合物在气态或液相中捕获氟化物和/或氟氧化物形式的金属的用途。 本发明还涉及具有式KMgF 3，比表面积至少等于30m 2 / g至多等于150m 2 / g的化合物及其制备方法。 本发明特别可用在核工业中，其中可有利地用于相对于所述物流中的金属杂质在气体或液体流中净化六氟化铀（UF 6）。
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公开(公告)号：WO2011121573A1
公开(公告)日：2011-10-06
申请号：PCT/IB2011/051408
申请日：2011-04-01
Applicant: THE SOUTH AFRICAN NUCLEAR ENERGY CORPORATION LIMITED , WAGENER, Jacobus, Beyers , PIENAAR, Andrew, Dirk , CARSTENS, Pieter, Andries, Blatt
CPC classification number: C01G35/02 , C01G33/00 , C01G35/00 , C01G43/066
Abstract: A process for treating a feedstock comprising tantalum- and/or niobium- containing compounds is provided. The process includes contacting the feedstock with a gaseous fluorinating agent, thereby to fluorinate tantalum and/or niobium present in the feedstock compounds. The resultant fluorinated tantalum and/or niobium compounds are recovered.
Abstract translation: 提供了一种处理含有钽和/或铌的化合物的原料的方法。 该方法包括使原料与气态氟化剂接触，由此使原料化合物中存在的钽和/或铌氟化。 回收所得到的氟化钽和/或铌化合物。
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公开(公告)号：WO98052872A1
公开(公告)日：1998-11-26
申请号：PCT/US1998/007163
申请日：1998-04-09
CPC classification number: G21F9/02 , C01G43/063 , G21F9/007 , G21F9/12
Abstract: Processes for the removal of technetium from contaminated uranium hexafluoride containing technetium, typically as technetium-99 ( Tc) in nominal chemical forms are provided. The processes involve contacting the contaminated uranium hexafluoride in liquid form with a metal fluoride, typically magnesium fluoride (MgF2), for a period of time sufficient for the technetium to become adsorbed onto the metal fluoride thereby producing a purified uranium hexafluoride liquid; and removing the purified uranium hexafluoride liquid from the metal fluoride having adsorbed technetium.
Abstract translation: 提供了从受污染的六氟化铀锝中除去锝的方法，通常以标称化学形式的锝-99（99℃）锝。 这些方法包括使污染的六氟化铀与金属氟化物（通常为氟化镁（MgF 2））接触一段足以使锝吸附到金属氟化物上的时间，从而产生纯化的六氟化铀液; 并从吸附有锝的金属氟化物中除去纯化的六氟化铀液。
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公开(公告)号：WO2023091924A1
公开(公告)日：2023-05-25
申请号：PCT/US2022/079925
申请日：2022-11-16
Applicant: METATOMIC, INC.
Inventor： BAER, Donald, Ken
Abstract: The present disclosure provides systems and methods for fast molten salt reactor fuel-salt preparation. In one implementation, the method may comprise providing fuel assemblies having fuel pellets, removing the fuel pellets and spent fuel constituents from the fuel assemblies, granulating the removed fuel pellets or process feed to a chlorination process, processing the granular spent fuel salt into chloride salt by ultimate reduction and chlorination of the uranium and associated fuel constituents chloride salt solution, enriching the granular spent fuel salt, chlorinating the enriched granular spent fuel salt to yield molten chloride salt fuel, analyzing, adjusting, and certifying the molten chloride salt fuel for end use in a molten salt reactor, pumping the molten chloride salt fuel and cooling the molten chloride salt fuel, and milling the solidified molten chloride salt fuel to predetermined specifications.
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公开(公告)号：WO2020123513A2
公开(公告)日：2020-06-18
申请号：PCT/US2019/065488
申请日：2019-12-10
Applicant: ALPHA TECH RESEARCH CORP.
Inventor： BENSON, John , MEMMOTT, Matthew
IPC: C01G43/06
Abstract: Some embodiments include a method comprising: flowing a molten salt out of a molten salt reactor at a first temperature, heating the molten salt reactor to a second temperature above the melding point of the second salt mixture causing the second salt mixture to melt; flowing the second salt mixture out of the molten salt reactor; flowing a third salt mixture into the molten salt reactor; and cooling the molten salt reactor from the second temperature to a third temperature causing the third salt mixture to solidify on the interior surface of the housing. In some embodiments, the molten salt may include a first salt mixture comprising at least uranium. In some embodiments, the first temperature is a temperature above the melting point of the first salt mixture.
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