GB1564079A - Process for the production of uranium plutoniumixed carbides - Google Patents

Process for the production of uranium plutoniumixed carbides Download PDF

Info

Publication number
GB1564079A
GB1564079A GB13281/77A GB1328177A GB1564079A GB 1564079 A GB1564079 A GB 1564079A GB 13281/77 A GB13281/77 A GB 13281/77A GB 1328177 A GB1328177 A GB 1328177A GB 1564079 A GB1564079 A GB 1564079A
Authority
GB
United Kingdom
Prior art keywords
plutonium
temperature
uranium
mixture
production
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB13281/77A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Forschungszentrum Karlsruhe GmbH
Original Assignee
Kernforschungszentrum Karlsruhe GmbH
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Kernforschungszentrum Karlsruhe GmbH filed Critical Kernforschungszentrum Karlsruhe GmbH
Publication of GB1564079A publication Critical patent/GB1564079A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01BNON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B32/00Carbon; Compounds thereof
    • C01B32/90Carbides
    • C01B32/914Carbides of single elements
    • C01B32/928Carbides of actinides
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01PINDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00Physical properties of inorganic compounds
    • C01P2006/80Compositional purity
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Organic Chemistry (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Description

(54) PROCESS FOR THE PRODUCTION OF URANIUM-PLUTONIUM-MIXED CARBIDES (71) We, KERNFORSCHUNGSZENTRUM KARLSRUHE GESELLSCHAFT MIT BESCHRAENKTER HAFTUNG, formerly, GESELLSCHAFT FUER KERNFORS CHUNG mbH of 75 Karlsruhe 1, Postfach 3640, Germany (Fed. Rep); a Germany body corporate do hereby declare the invention, for which we pray that a patent may be granted to us, and the method by which it is to be performed, to be particularly described in and by the following statement: The present invention relates to a process for the production of uranium-plutoniummixed carbides, in which a mixture of uranium dioxide, plutonium dioxide and graphite is subjected to a carbothermal reduction.
Whilst the production of uranium carbide is characterised by technological difficulties with regard to extraction of possibly phase-pure products, additional problems arise during the production of uranium-plutonium-mixed carbides by the peritectic decomposition of plutonium carbide. Besides weight losses, there also occurs a carbon enrichment of the samples which leads to sesquicarbide formation. In pure plutonium carbide, from about 157 K considerable weight losses are already observed, whilst in samples containing uranium carbide having above 30 mol % uranium carbide in solid solution, the peritectic decomposition of the plutonium carbide is clearly reduced. Quantiative investigations resulted for the plutonium steam pressure: of pure PuC . log Ppu = 4.686 - 18091/T (atm) (1761-1907 K) of U085Pu0el5C : log Ppu = 5.47 - 23000/T (atm) (1700-2000 K) The effects of carbide decomposition on the production of specific carbide fuels are manifold, e.g. the specific Pu/U+Pu ratio, and also the stoichiometric composition, changes during the manufacturing process. Therefore, for carbide manufacture it is necessary to have an exact knowledge of the rates of plutonium loss which are, in any case, plant-related. For industrial production of mixed carbide fuel, moreover, economic and safety technological questions arise. Fissionable material occurring as plutonium loss during production remains in the processing plant and on the one hand collects in the plant regions which are particularly inaccessible; on the other hand the plutonium quantities not returnable to the manufacturing process increase the manufacturing costs, which in processes applied heretofore amount to substantially between 1.5 and 2% by weight.
The full synthesis process proceeds as the most simple of the known processes from a mixture of a metal oxide with carbon. Due to the common carbothermal reduction a mixed carbide is extracted which is then available as starting product for the production of pellet fuel by sintering. The whole production process is thus schematically described by the following equations: x U02 + (1-x) PuO2 + 3 C o (UxPul-xc) + 2 CO (reduction) (uxpul-xc) < UxPul c (sintering) The object of the invention is now to provide a process which at least minimizes the disadvantages of known processes and reduces plutonium losses.
According to the present invention there is provided a process for the production of uranium-plutonium-mixed carbides, in which a mixture of uranium dioxide, plutonium dioxide and graphite is subjected to a carbothermal reduction, characterised by the process steps in the established sequence: a) grinding a mixture of uranium dioxide, plutonium dioxide and graphite for a grinding period of from 1 to 3 hours; b) heating the ground mixture of a) to a temperature of 1600 K or above until the onset of carbothermal reduction for the mixed carbide core formation indicated by the commencement of carbon monoxide production; c) cooling the reaction mixture to a temperature in the region of from 1300 K to 1550 K; d) maintaining a constant temperature after cooling, until completion of a first part stage of the carbothermal reduction recognized by the abatement of carbon monoxide production, and e) continued heating of the reaction mixture to form a single phase, substantially oxygen-free uranium-plutonium-mixed carbide at a temperature of from 1800 K to 1850 K, completion of a second part stage of the carbothermal reduction occurring therewith and subsequent cooling of the end product.
It has been found that the carbothermal reduction of a mixture of UO2, PU2 and graphite takes place in two stages. In the first stage, there is formed a mixture of oxide, oxicarbide (U,Pu)(Ox,Cl-x) and sesquicarbide, which still contains carbon in varying proportions7 and in the second stage this mixture then comprises the required mixed carbide. Thus, the effectiveness of the first reaction stage is dependent upon the powder preparation, whilst the effectiveness of the second stage on the other hand is independent thereof.
Experiments, in which the starting materials are first mixed and ground each for a period of 2, 4, 8, 16 or 32 hours, have shown that in the samples with the longer grinding period the carbothermal reduction sets in at a lower temperature than in the other samples. Moreover, it was possible to observe that the separation of the two reaction stages became clearer with an increasing grinding period and the reproductability of the process is improved.
To have a deeper insight into the operations during the carbothermal formation of the uranium and plutonium carbides, a number of samples were subjected to radiographic phase analysis according to different reactions. These investigations have shown that the reaction behaviour of uranium dioxide-plutonium dioxide-graphite mixtures, have to be slit up into three fundamental cases: a) in the case of mixed, and not ground, powder the two above-mentioned reaction stages for the uranium- and the plutonium-containing phases occur substantially independently of one another in parallel.
b) in powders which were mutually ground for 36 hours, the mixed crystals (U0.8Pu0.2)O2 forms before the inset of carbide formation. Then in the first reaction stage there occurs the formation of (U,Pu)(Ox,Cl.x) and (U,Pu)2C3, which in the next stage react mutualy with the residual free carbon to form (U,xPuo.)C.
c) if the powders are not ground for such a long period, though no pure mixed oxide is any longer produced. the carbide formed, dependent upon the grinding period, however, contains mixed carbide to a greater proportion.
On account of the intermediate products, it has to be assumed that in the case of the synthesis of the mixed carbide, the various stages are determined by the plutonium, since in the samples in which the two starting dioxides were present only in a mixed state, the carbothermal reduction of both oxides occurring substantially independently of one another, it is also comprehensible that the kinetics of this operation is determined by the compounds of the excess uranium present.
Whilst long grinding periods have been found effective in reducing the plutonium losses, such procedure accounts for an increase in expenditure in time, costs and apparatus for industrially applicable processes. For this reason for optimising the process further investigations were carried out which are described below.
The investigation results of the high activation energy at the start of the reaction in samples which were made of powders only ground for a short period, permit the conclusion to the expiration of a core forming operation. This core forming in a uranium dioxide-graphite mixture ground for 36 hours obviously occurs already during the grinding process.
The hypothesis of the core formation may be proved in that a mixture of uranium dioxide, plutonium dioxide and graphite ground for two hours is heated until the carbothermal reduction process sets in and then suddenly cooling it. If on reheating the reaction occurs at a substantially low temperature, core formation is present. During the first reheating the reaction sets in at about 1655 K. After cooling and reheating the reaction began at 1390 K, thus 265 K lower. This is a clear proof of the existence of core formation.
Independently of the powder preparation, a single phase monocarbide, Iow in oxygen, may be produced only at temperatures above 1800 K.
The invention is described by way of an example and a diagram for the reaction course of this example shown in the accompanying drawing. The invention, however, is not limited to this example and this diagram.
Example: 274 mg of a mixture of U02, PuO2 and graphite, in which the ratio of UO2 to PuO2 amounted to 80 to 20 (percent by weight), and the quantity of graphite corresponded to a quantity stoichiometrically required for conversion, were at first ground for 2 hours and then for 80 minutes with a constant heating up rate (approx. 18 degrees/minute) were brought to a temperature of 1753 K. The noticeable CO reduction showed the onset of the carbothermal reduction (first part stage). The reaction mixture thereupon was suddenly cooled off to 1543 K and kept at this temperature for 4.5 hours. With a rapid further heating up to 1823 K the carbothermal reduction was terminated (end of second part stage). The temperature was held for a period of 60 minutes for forming a single phase, substantially oxygen-free, U0 8PUo 2C and subsequently slowly cooled off by shutting down the furnace.
furnace.
The analysis of the cooled end product showed a plutonium loss of only approximately 0.5% by weight.
The process in accordance with the invention also provides the advantage that it permits a considerable economy of electric energy by the reduction of the reaction temperature.
WHAT WE CLAIM IS: 1. A process for the production of uranium-plutonium-mixed carbides in which a mixture of uranium dioxide, plutonium dioxide and graphite is subjected to a carbothermal reduction, characterised by the process steps in the established sequence: a) grinding a mixture of uranium dioxide, plutonium dioxide and graphite for a grinding period of from 1 to 3 hours; b) heating the ground mixture of a) to a temperature of 1600 K or above until the onset of carbothermal reduction for the mixed carbide core formation indicated by the commence- ment of carbon monoxide production; c) cooling the reaction mixture to a temperature in the region of from 1300 K to 1550 K; d) maintaining a constant temperature after cooling until the completion of a first part stage of the carbothermal reduction noticeable by the abatement of carbon monoxide production; and e) continued heating of the reaction mixture to form a single phase, substantially oxygen-free uranium-plutonium-mixed carbide at a temperature of from 1800 K to 1850 K, completion of a second part stage of the carbothermal reduction occuring therewith and subsequent cooling of the end product.
2. A process for the production of uranium-plutonium-mixed carbides, substantially as hereinbefore described, exemplified and illustrated in the accompanying drawing.
**WARNING** end of DESC field may overlap start of CLMS **.

Claims (2)

**WARNING** start of CLMS field may overlap end of DESC **. The invention is described by way of an example and a diagram for the reaction course of this example shown in the accompanying drawing. The invention, however, is not limited to this example and this diagram. Example: 274 mg of a mixture of U02, PuO2 and graphite, in which the ratio of UO2 to PuO2 amounted to 80 to 20 (percent by weight), and the quantity of graphite corresponded to a quantity stoichiometrically required for conversion, were at first ground for 2 hours and then for 80 minutes with a constant heating up rate (approx. 18 degrees/minute) were brought to a temperature of 1753 K. The noticeable CO reduction showed the onset of the carbothermal reduction (first part stage). The reaction mixture thereupon was suddenly cooled off to 1543 K and kept at this temperature for 4.5 hours. With a rapid further heating up to 1823 K the carbothermal reduction was terminated (end of second part stage). The temperature was held for a period of 60 minutes for forming a single phase, substantially oxygen-free, U0 8PUo 2C and subsequently slowly cooled off by shutting down the furnace. furnace. The analysis of the cooled end product showed a plutonium loss of only approximately 0.5% by weight. The process in accordance with the invention also provides the advantage that it permits a considerable economy of electric energy by the reduction of the reaction temperature. WHAT WE CLAIM IS:
1. A process for the production of uranium-plutonium-mixed carbides in which a mixture of uranium dioxide, plutonium dioxide and graphite is subjected to a carbothermal reduction, characterised by the process steps in the established sequence: a) grinding a mixture of uranium dioxide, plutonium dioxide and graphite for a grinding period of from 1 to 3 hours; b) heating the ground mixture of a) to a temperature of 1600 K or above until the onset of carbothermal reduction for the mixed carbide core formation indicated by the commence- ment of carbon monoxide production; c) cooling the reaction mixture to a temperature in the region of from 1300 K to 1550 K; d) maintaining a constant temperature after cooling until the completion of a first part stage of the carbothermal reduction noticeable by the abatement of carbon monoxide production; and e) continued heating of the reaction mixture to form a single phase, substantially oxygen-free uranium-plutonium-mixed carbide at a temperature of from 1800 K to 1850 K, completion of a second part stage of the carbothermal reduction occuring therewith and subsequent cooling of the end product.
2. A process for the production of uranium-plutonium-mixed carbides, substantially as hereinbefore described, exemplified and illustrated in the accompanying drawing.
GB13281/77A 1976-05-15 1977-03-30 Process for the production of uranium plutoniumixed carbides Expired GB1564079A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2621743A DE2621743C3 (en) 1976-05-15 1976-05-15 Process for reducing plutonium losses in uranium-plutonium mixed carbide production

Publications (1)

Publication Number Publication Date
GB1564079A true GB1564079A (en) 1980-04-02

Family

ID=5978123

Family Applications (1)

Application Number Title Priority Date Filing Date
GB13281/77A Expired GB1564079A (en) 1976-05-15 1977-03-30 Process for the production of uranium plutoniumixed carbides

Country Status (3)

Country Link
DE (1) DE2621743C3 (en)
FR (1) FR2351050A1 (en)
GB (1) GB1564079A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6214309B1 (en) * 1997-09-24 2001-04-10 University Of Connecticut Sinterable carbides from oxides using high energy milling

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1051035A (en) *
GB948791A (en) * 1960-12-02 1964-02-05 Atomic Energy Authority Uk Improvements in or relating to the production of uranium and plutonium monocarbides
BE754787A (en) * 1969-08-16 1971-01-18 Nukem Gmbh DEVICE FOR NON-VAPORIZATION MELTING OF URANIUM CARBIDE AND PLUTONIUM CARBIDE

Also Published As

Publication number Publication date
FR2351050B1 (en) 1982-07-09
DE2621743A1 (en) 1977-11-24
FR2351050A1 (en) 1977-12-09
DE2621743B2 (en) 1978-04-13
DE2621743C3 (en) 1978-12-07

Similar Documents

Publication Publication Date Title
US2906598A (en) Preparation of high density uo2
US4235740A (en) Method for the manufacture of (U,Pu)O2 mixed crystals
WO2019018082A2 (en) A method to produce uranium silicides
US2868707A (en) Process of making a neutronic reactor fuel element composition
US4234550A (en) Method for treating a particulate nuclear fuel material
JP2905294B2 (en) Method for producing UO2 fuel pellets from uranium metal without producing waste
DE2262868C3 (en) Process for the production of pure monocarbides, mononitrides and carbonitrides
CA1172438A (en) Treatment of fuel pellets
CN111655623B (en) Method for preparing a powder based on an oxide comprising uranium and plutonium using a mixture of specific organic ligands and use of this powder for manufacturing a fuel based on uranium and plutonium
US3275564A (en) Process of fabrication of sintered compounds based on uranium and plutonium
GB1564079A (en) Process for the production of uranium plutoniumixed carbides
US3046090A (en) Production of uranium monocarbide
US3320034A (en) Conversion of uo to uc
RU2110856C1 (en) Method for recovery of uranium isotope mixture burnt-out in nuclear reactor
US3879520A (en) Method for dissolving ceramic beryllia
US3037839A (en) Preparation of uo for nuclear reactor fuel pellets
US3288568A (en) Direct dissolution of water-insoluble uranium compounds by contact with neutral organic solvents pretreated with nitric acid
JPS6173803A (en) Production of powder mixture composed of uranium dioxide and gadolinium oxide for producing nuclear fuel pellet
US3386811A (en) Preparation of an actinide metal monocarbide from an oxide thereof
US3937784A (en) Method for removing fluoride ions from UO2 powders
DE3871671T2 (en) METHOD FOR PRODUCING URANE AND / OR PLUTONIUM NITRIDE, USED AS A FUEL MATERIAL.
CA1093279A (en) Process for the preparation of uranium dioxide
US5417943A (en) Method for producing UO2 or (U/PU)02 powder
CA1109663A (en) Method for treating a particulate nuclear fuel material
JP2004131348A (en) Method for producing uranium oxide

Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee