WO2007053128A1 - Procede de transformation de combustible nucleaire usage et installation destinee a sa mise en oeuvre - Google Patents

Procede de transformation de combustible nucleaire usage et installation destinee a sa mise en oeuvre Download PDF

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Publication number
WO2007053128A1
WO2007053128A1 PCT/UA2005/000047 UA2005000047W WO2007053128A1 WO 2007053128 A1 WO2007053128 A1 WO 2007053128A1 UA 2005000047 W UA2005000047 W UA 2005000047W WO 2007053128 A1 WO2007053128 A1 WO 2007053128A1
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Prior art keywords
fuel
fluorides
fluorination
nuclear fuel
plutonium
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PCT/UA2005/000047
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English (en)
Russian (ru)
Inventor
Alexander Ivanovich Karelin
Vladimir Aleksandrovich Karelin
Ravil Abdurahimovich Abubekerov
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S.T.B. Advanced Technology Ltd
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Priority to PCT/UA2005/000047 priority Critical patent/WO2007053128A1/fr
Publication of WO2007053128A1 publication Critical patent/WO2007053128A1/fr

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48—Non-aqueous processes
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Definitions

  • the proposed invention relates to a technology for the production of nuclear fuel, and in particular, to methods and devices for the manufacture of fuel from products from the processing of spent nuclear fuel (SNF).
  • SNF spent nuclear fuel
  • spent nuclear fuel reprocessing technology is the Purex process.
  • spent nuclear fuel containing uranium and plutonium is dissolved in nitric acid, after which the nitric acid solution is treated with the organic phase obtained by diluting the TBP (tributyl phosphate) extracting agent with dodecane, isolating it from the solution, and then and purifying uranium and plutonium, which enter the organic phase more easily than most other decay products.
  • TBP tributyl phosphate
  • spent nuclear fuel is dissolved in nitric acid and the resulting solution is then treated in a so-called joint purification unit, in which uranium and plutonium, which are jointly cleaned from decay products, are extracted from nitric acid solution using an organic solution diluted in Dean of TBF.
  • the extract obtained by the joint purification of uranium and plutonium from decay products using an organic solution, which contains uranium and plutonium, is then processed in a so-called distribution (separation) installation, in which uranium is separated from plutonium.
  • a solution in which uranium and plutonium were initially contained and in which decay products remained It is treated as highly radioactive liquid waste.
  • an organic solution containing uranium and plutonium is mixed with a solution of nitric acid, while plutonium, which is reduced to trivalent plutonium, goes back from the organic phase to a solution of nitric acid. Separation of plutonium and uranium is carried out, which remains in the organic phase.
  • the uranium and plutonium separated at the distribution unit are then separately purified, after which the purified plutonium and purified uranium can again be used as nuclear fuel.
  • JP 09-138297 The Purex method for processing spent nuclear fuel described in JP 09-138297 differs from traditional methods in its simpler technology and higher efficiency, which reduces the amount of liquid (radioactive) waste generated during the processing of spent nuclear fuel, but it does not allow create a closed technological process - the production of nuclear fuel from spent nuclear fuel.
  • the described method is based on fluoride-extraction processing of spent nuclear fuel - the so-called fluorine-aqua process. This is a combination of fluoride and extraction technologies.
  • the disadvantage of the described method is that it does not allow to create a closed technological process - the use of nuclear fuel and the subsequent reprocessing of spent nuclear fuel into new nuclear fuel. This, in particular, is due to the fact that: - to date, devices for fluorination of SNF powders in a radiochemical design have not been developed;
  • the basis of the proposed inventions is the task of creating such a method and installation for SNF reprocessing that would allow creating a closed technological process, including the use of nuclear fuel at nuclear power plants and the subsequent reprocessing of SNF in the NPP into new nuclear fuel, for example, for the same nuclear power plant.
  • This problem is solved by creating conditions for the cycle (recycling) of elemental fluorine.
  • the problem is solved by the proposed method, which, like the known method of SNF processing, includes its treatment with fluorine or a fluorine-containing compound, and, according to the invention, processing
  • the spent nuclear fuel pellets are produced in gaseous reverse fluorine in two stages with distillation of 85-90% of uranium hexafluoride in the first fluorination stage and a mixture of uranium and plutonium hexafluorides in the second stage at a temperature of 300-800 0 C in a column type apparatus with internal heat removal of chemical reactions for due to the selection of part of the gas phase of the products of fluorination reactions, cooling of this part of the gas phase with a coolant and return (circulation) to the fluorination apparatus, further evolution of oxygen formed in the processes of second stage of fluorination nuclear fuel oxide by the use of the temperature difference and the boiling oxygen formed fluorides, fluorides distillation purification fissile actinide elements from fission product fluorides, fluorides electrolytic
  • the problem is solved in the proposed installation, which, like the well-known installation for the reprocessing of spent nuclear fuel, contains a control panel, a protective chamber in which are installed remotely controlled devices for the mechanical cutting of spent fuel pellets, the drive mechanisms of the devices for mechanical cutting of which are connected to the control panel, and, according to the invention, the installation is additionally equipped with a device for the manufacture of tablets of oxide and mixed uranium-plutonium fuel, a device for vacuum distillation of zinc from metal actinide powders, an electrolyzer designed for electrolytic reduction of fluorides to produce metal powders and gaseous elemental fluorine, as well as a fluorination apparatus, which includes a column-type fluorination reactor with a fluidized bed of fuel pellet material connected to a fine filter of the gas phase from dust, connected to a heat exchanger for cooling gases and with a condenser for sublimation of fluorides and the release of inert gases connected to a distillation column for purifying fluorides of fissile elements from
  • the installation in addition, is equipped with a pneumatic conveying system for powders, a gas flow inducer, control devices and an automatic process control system.
  • the resulting silicon-silicides composites, fission products of americium silicides and curium-silicon dioxide are packed in sealed ceramic ampoules of boron nitride, titanium boride or silicon boride with the latter installed in sealed ceramic containers made of silicon carbide or silicon nitride and sent to underground station dry storage for burial.
  • the proposed inventions make it possible to create an effective and environmentally friendly technology for reprocessing spent nuclear fuel with the possibility of multiple use of fissile materials, the isolation of radioactive fission products and their immobilization in the form of silicides, carbides, borides in an insoluble form of a silicon-containing composite.
  • the invention involves the creation of a single automated energy complex "nuclear reactor burning fissile materials with thermal or fast neutrons - a line substation radiochemical plant with its location underground in a metal case with sealing of all inputs and outputs of communications, all inputs and outputs of technical personnel a well-established method of sealing a submarine. "nuclear reactor burning fissile materials with thermal or fast neutrons - a line substation radiochemical plant with its location underground in a metal case with sealing of all inputs and outputs of communications, all inputs and outputs of technical personnel a well-established method of sealing a submarine.
  • elemental fluorine without an admixture of hydrogen fluoride, intermediate products - anhydrous fluorides of actinides, lanthanides, etc. are used as the main reagent-oxidant, and a constant electric current is used as a reducing agent using electrolytic processes in low-melting fluoride salt melts.
  • These inorganic substances have radiation and neutron resistance, do not form explosive mixtures.
  • the proposed inventions make it possible to reprocess spent nuclear fuel with a complete NFC closure within the production site of each nuclear power plant, with the exception of the transportation of fissile materials and highly radioactive substances over long distances by land and water.
  • Creation of unified automated of energy complexes "a nuclear reactor burning fissile materials - a substation radiochemical plant with its location underground in a metal case with sealing of all inputs and outputs of communications and technical personnel using a well-developed submarine method” allows you to create the necessary number of safety barriers and completely eliminate the possibility of its destruction both due to man-made (flood, earthquake, tornado, etc.), unintentional (plane crash, etc.) and deliberate terrorism tical influences. This result is due to the following distinctive features.
  • fluorination is carried out by circulating elemental fluorine without grinding pellets of spent fuel, which eliminates the dusting of radioactive substances and seals technological equipment.
  • the fluorination process is carried out in the temperature range of 300-800 ° C.
  • the heat released during fluorination of oxides is removed not through the walls of the equipment, but inside the column reactor volume by taking part of the gas phase of the oxidation reaction products, cooling and returning it (circulation through an external heat exchanger), and returning it to the fluorination apparatus with a stationary layer of spent fuel tablets, as shown in fig. 2.
  • Another distinctive feature of the proposed method SNF processing is the electrolytic reduction of fission product fluorides in a melt of a low melting eutectic of fluoride salts at 500-550 ° C to fissile metals in the form of a powder on a molten zinc zinc cathode.
  • the electrolytic system itself is new, which consists of a melt of the eutectic of ternary fluoride salts of alkali metals LiF-KF-NaF with a melting point of 472-500 0 C, i.e. chemical compounds containing fluorine, and the saturation of this melt is carried out with gaseous hexafluorides of uranium, plutonium and neptunium, i.e. chemical compounds that also contain fluorine.
  • the electrolytic system consists only of fluoride compounds. This makes it possible in one stage to obtain electrolytically pure metal fission products (uranium, plutonium) at the cathode, and pure elemental fluorine at the anode, the cost of which is much lower than the cost of these substances obtained by known technologies and methods.
  • the melt of the eutectic of fluoride salts LiF-ICF-NaF is saturated with gaseous hexafluorides of uranium, plutonium, neptunium in the range of 2-20% in the amount of fluorides.
  • a parameter below 2% requires the supply of a large amount of energy (in coulomb), and a parameter above 20% leads to an increase in the melting point of the eutectic of fluoride salts, which is also undesirable.
  • the electrolysis efficiency increases if the saturation of the eutectic melt of the ternary system of alkali metal fluoride salts is carried out by bubbling the gaseous salts of uranium, plutonium and neptunium hexafluorides into the melt. This is because bubbling under the eutectic melt layer ensures complete absorption of the hexafluoride mixture and their uniform saturation of the molten electrolyte with higher fluorides of the starting elements from the gas mixture.
  • a distinctive feature of the proposed method is that for the allocation of processed products do not need to stop the process electrolysis, the removal of metal powders of fissile elements in a mixture with a molten electrolyte and a molten zinc (liquid cathode) can be carried out in a continuous mode.
  • the continuous withdrawal of a suspension of metal powders of fissile elements and zinc is also facilitated by the fact that the density of metal powders exceeds the density of the zinc melt by more than 2-2.5 times, therefore, the surface of the liquid melt of the cathode is continuously cleaned.
  • the gaseous elemental fluorine that is released from the anodes is continuously removed and sent for reuse for the fluorination of the original tablets of spent nuclear fuel.
  • SNF is treated with gaseous reverse fluorine at a temperature of 300-800 0 C, since at a temperature below 300 0 C non-volatile fluorides (fluoride cinder) adhere to the inner surface of the walls of the fluorination reactor, and at temperatures above 800 0 C there are cases of burn-out of the walls of the fluorination reactor .
  • the electrolytic reduction of fluorides of fissile actinide elements in a melt of a low-melting eutectic of ternary fluoride salts of alkaline elements is carried out at a temperature of 500-550 0 C.
  • the process of immobilization of all gaseous and non-volatile fluorides of fission products in a silicon melt is carried out at a temperature of 1420-1450 0 C, since at a temperature below 1420 0 C, the formed melt solidifies, and at a temperature above 145O 0 C, the degree of capture of gaseous and non-volatile fluorides of fission products is significantly reduced (about 5 times).
  • the fission products were immobilized in a silicon melt, and the resulting composite was packaged in ceramic ampoules and containers based on the results of the experiments of the authors with unirradiated materials.
  • FIG. 1 schematically presents one of the options for the technological process of processing spent MOX fuel into at the substation plant - the technological process of reprocessing SNF of the BBEP-1000 reactor and manufacturing of fuel elements and TBC in accordance with the proposed method
  • FIG. 2 is a diagram illustrating the step of fluoridation of spent nuclear fuel tablets with elemental fluorine with internal heat dissipation
  • FIG. 3 a diagram of an electrolyzer for producing metal powders of fissile elements and elemental fluorine is presented.
  • the proposed SNF reprocessing facility comprises a control panel, a protective chamber in which remotely controlled devices for mechanical cutting of spent fuel pellets (TT) are installed, the drive mechanisms of the mechanical cutting devices of which are connected to the control panel / not shown /.
  • the installation is equipped with a fluorination apparatus, which includes a column type fluorination reactor 1 with a fluidized bed of tablet material, a flow inducer 2, a heat exchanger 3 for cooling gases, a dust filter 4 for fine cleaning the gas phase, which are combined into a single technological chain.
  • the column-type fluorination reactor 1 with a fluidized bed of tablet material contains a TT loading device, a fitting equipped with a valve, for introducing elemental fluorine, a fitting equipped with a valve, for withdrawing and vacuum transporting non-volatile fluorides to packaging and disposal and a fitting equipped with a valve, for outputting volatile fluorides of PD, UF 6 , PuF 6 , NpF 6 , F 2 (v, zb) 5 O 2 and their direction to the fine filter 4, one output of which is intended for directing to condensation UF 6 , PuF 6 , NpF 6 volatile fluoride PD, and the second, equipped for vizhkoy, connected to the inlet of the heat exchanger 3 for cooling the gases, whose output is connected to the inlet of flow boosters 2, whose output is connected to the input for input of elemental fluorine in the fluorination reactor 1.
  • a TT loading device a fitting equipped with a valve, for introducing elemental fluorine
  • the device is connected to the capacitor fluorides actinides and PD at -60 0 C, equipped with special traps, cooled with liquid nitrogen, where actinide fluorides, volatile and low-volatile fluorides, PD are subjected to 2-stage distillation purification / not shown /. Since the gas mixture of TT fluorination products has a high heat capacity, the installation includes an automatic device for regulating cooling processes to remove heat, depending on the set temperature in the TT fluorination apparatus.
  • the unit is equipped with a pneumatic conveying device designed for transfer to packaging in sealed capsules of ceramic structural powders of titanium diboride (T 1 B2) or boron nitride (BN).
  • the installation is equipped with an electrolytic cell for electrolytic reduction of actinide fluorides purified from PD to metal powders in a melt of eutectic fluoride salts at a temperature of 500-550 0 C.
  • the electrolyzer contains a housing 5, in which a graphite anode is installed 6.
  • Anodic current supply is installed on housing 5. 7.
  • a liquid zinc anode 8 is placed, and a cathodic current supply 9 and an electrical isolation and exhaust assembly F 2 - 10 are located on the housing 5.
  • the housing 5 is equipped with an electrically insulated support assembly 11.
  • the housing 5 has a graphite 12.
  • the fitting 1 is fitted with a fitting 1 3 for draining the liquid cathode into a container 14 and a zinc evaporator 15.
  • the installation also includes an automatic process control system and a device for manufacturing fuel pellets of mixed uranium-plutonium fuel from the obtained powder materials.
  • the determining operations on which the properties of the finished tablets depend are pressing and sintering.
  • the proposed installation uses a known device containing single-point matrices with two-sided application of pressing pressure. This process is carried out on a high-performance fully automated press.
  • the press has a rotating tabletop, in which there are 10 socket molds, grouped in sections. In the mold of each section passing certain press positions, sequentially, the operations of loading press powder, pressing, pressing and extracting fuel pellets are performed (see Development, production and operation of fuel elements of power reactors. Book l. Edited by SG Reshetnikov. - M .: Energoatomizdat, 1995, p. 292-296) / not shown /.
  • the fluoride technology for spent nuclear fuel (SNF) regeneration is based on the ability of the main components of fuel compositions - uranium and plutonium - to form higher fluorides - uranium and plutonium hexafluorides by reactions:
  • the bulk of radionuclides - PD (alkaline, alkaline-earth, rare-earth elements, etc.) forms non-volatile or low-volatile fluorides, which are easily removed from the process in solid form at the initial stage of SNF processing. Differences in the volatility of fluoride compounds allow deep purification of uranium and plutonium from all PD.
  • Fig. 1 schematically illustrates one embodiment of a process for reprocessing spent MOX fuel at a substation plant.
  • Figure 1 shows the composition of the actinides of the fragmentation elements in the annual discharge of the WER reactor.
  • the TBC assembly enters the sealed chamber for uncasing the assembly, cutting the shanks, plugs and cutting the fuel rods.
  • the metal parts of the assembly, shanks and pieces of shells of fuel elements in the amount of 19.7 tons / year are remelted with separation into pure metal ingots and approximately 5% in May. contaminated slag ( ⁇ 1 t / year).
  • Slag is packaged in sealed ceramic ampoules and containers, which are stored in dry dry underground compartments.
  • Part of the gaseous fission products (PD) from the cutting and cutting chamber is fed to the stable xenon compartment, which is used for its intended purpose, the remaining PD are pumped and stored in cylinders. In total, no more than 2.5 m 3 / year from one VVER-1000 reactor should be stored.
  • Tablets of irradiated fuel in an amount of 440 kg are sent to the fluorination reactor 1 by circulating elemental fluorine.
  • the fluorination reactor 1 an apparatus made of stainless steel is used, which is internally coated with a thin dense nickel film.
  • Reactor 1 has a false bottom onto which a stationary layer of fuel pellets (TT) is poured without crushing them.
  • Reverse elemental fluorine is fed under the false bottom from May 15-20%. excess relatively stoichiometrically necessary amount and carry out the process of fluorination according to the reactions:
  • Reactions (3-5) are autogenous, they do not require heat supply, on the contrary, it is necessary to remove the generated heat (Qi + Q 2 + Q 3 ).
  • Heat removal is carried out forcefully by taking part of the gas stream (UF 6 (D, PuFV) 5 NpF 6 (D, F 2 ( G ) Iz6 , OVD) after the reactor fluoridation, its cooling and circulation through the fluorinated TT layer.
  • the gas mixture of TT fluorination products has a high heat capacity, its volume for circulation, cooling for heat removal is automatically regulated, depending on the set temperature in the TT fluorination apparatus.
  • a diagram of a fluorination apparatus TT with an excess heat removal system is shown in FIG. 2.
  • TT fluorination process is carried out in two stages in two stages with distillation of 85-90% of uranium hexafluoride in the first fluorination stage and a mixture of uranium and plutonium hexafluorides in the second stage at a temperature of 300-800 0 C. After the second fluorination stage, the process is stopped. Non-volatile fluorides of the elements are transferred by means of pneumatic transport to the packaging in sealed capsules made of ceramic structural powders of titanium diboride (TiB 2 ) or boron nitride (BN).
  • TiB 2 titanium diboride
  • BN boron nitride
  • Capsules with non-volatile PD fluorides are installed in sealed ceramic containers made of silicon carbide or silicon nitride (SiC or Si 3 N 4 ) and sent for burial in underground dry storage. In total, ⁇ 0.3 tons of non-volatile fluorides are formed and sent to the disposal site.
  • the gas phase from the fluorination reactor 1 after fine filtration on a fine filter 4 is directed to the condensation of actinide fluids and PD at -60 ° C in special traps cooled with liquid nitrogen.
  • Actinide fluorides, volatile and low-volatile fluorides PD are subjected to 2-stage distillation treatment.
  • Actinoid fluorides purified from PD are fed for electrolytic reduction to metal powders in a melt of eutectic fluoride salts at 500-550 ° C, actinide powder is removed from the electrolyzer (Fig. 3) in a mixture with part of the molten zinc.
  • Zinc is removed from the suspension by vacuum distillation. Zinc return to the electrolyzer to replenish the liquid cathode, and metal powders are oxidized with air and sent to the manufacture of fuel elements and TBC. To carry out the process of electrolysis of metal actinide powders, only one electrolyzer with an electric load of 12.5 kA is needed for the performance of the mini-plant.
  • Non-condensed PD fluorides BF 3 , CF 4 , etc.
  • oxygen released at the TT fluorination stage excess fluoride from the fluorination stage
  • volatile and low-volatile PD fluorides from the 1st and 2nd stages of rectification purification of actinide fluorides are sent to absorption molten silicon. In this melt, all of the above gaseous substances are absorbed by the reactions:
  • the resulting composite Si-SiB 2 -SiC-SiO 2 -PD silicides in the amount of 22.313 t / year are packed in sealed ceramic ampoules of BN, TiB 2 or SiB 2 and ceramic containers of SiC or Si 2 N 4 .
  • Composite PD material in ceramic ampoules and containers is sent to an underground station storage facility for disposal.
  • Gaseous silicon tetrafluoride released by reactions (6–9) is electrolytically reduced to produce silicon powder and elemental fluorine. Elemental fluorine from the inert anodes of all electrolytic cells is used in recycling for TT fluorination, and silicon melt is used to capture PD fluorides.
  • the fluoride technology is practically reagent-free, since the main chemical reagent for opening the spent oxide fuel - elemental fluorine released on the anodes during electrolysis, is repeatedly used in its own recycling during TT fluorination; radioactive PDs are completely recovered in concentrated form in solid insoluble form in the amount of

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

L'invention appartient au domaine de la transformation de combustible nucléaire usagé. Selon l'invention, le procédé de transformation de combustible nucléaire usagé comprend le traitement dudit combustible avec du fluor. Le traitement des pastilles de combustible nucléaire usagé se fait avec du fluor recyclé en deux stades, avec la sublimation de 85-90 % d'hexafluorure d'uranium au premier stade de fluoration et d'un mélange d'hexafluorures d'uranium et de plutonium au deuxième stade, à une température de 300-800 °C. On effectue une réduction électrolytique des fluorures d'éléments fissibles d'actinides dans un bain de fusion eutectique à point de fusion bas des triples sels de fluorures d'éléments alcalins à une température de 500-550°, accompagnée d'un dégagement simultané de fluorures et d'éléments fissiles. On fabrique des pastilles d'un combustible mixte uranium / plutonium. L'installation de transformation de combustible nucléaire usagé comprend un tableau de commande, une chambre de protection dans laquelle on a monté des dispositifs pilotés à distance, destinés à la séparation mécanique des pastilles de combustible usagé, et des mécanismes d'entraînement connectés au tableau de commande. L'installation comprend également un dispositif de fabrication de pastilles d'un combustible mixte uranium / plutonium, un électrolyseur et un appareil de fluoration. Les avantages de l'invention sont une consommation réduite et une plus grande sécurité nucléaire.
PCT/UA2005/000047 2005-11-02 2005-11-02 Procede de transformation de combustible nucleaire usage et installation destinee a sa mise en oeuvre WO2007053128A1 (fr)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010014745A2 (fr) * 2008-07-29 2010-02-04 Battelle Memorial Institute Systèmes et procédés de traitement de matériau

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Publication number Priority date Publication date Assignee Title
GB1198454A (en) * 1966-09-06 1970-07-15 Ct D Etude De L En Nucleaire C Method for Reprocessing Nuclear Fuel
US4880506A (en) * 1987-11-05 1989-11-14 The United States Of America As Represented By The Department Of Energy Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels
RU2226725C2 (ru) * 2001-03-02 2004-04-10 Хитачи, Лтд. Способ переработки отработанного ядерного топлива (варианты)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1198454A (en) * 1966-09-06 1970-07-15 Ct D Etude De L En Nucleaire C Method for Reprocessing Nuclear Fuel
US4880506A (en) * 1987-11-05 1989-11-14 The United States Of America As Represented By The Department Of Energy Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels
RU2226725C2 (ru) * 2001-03-02 2004-04-10 Хитачи, Лтд. Способ переработки отработанного ядерного топлива (варианты)

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Title
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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010014745A2 (fr) * 2008-07-29 2010-02-04 Battelle Memorial Institute Systèmes et procédés de traitement de matériau
WO2010014745A3 (fr) * 2008-07-29 2010-03-25 Battelle Memorial Institute Systèmes et procédés de traitement de matériau
US8867692B2 (en) 2008-07-29 2014-10-21 Battelle Memorial Institute Systems and methods for treating material

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