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WO2002050845A1 - Pastille de combustible nucleaire et procede de fabrication - Google Patents

Pastille de combustible nucleaire et procede de fabrication Download PDF

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Publication number
WO2002050845A1
WO2002050845A1 PCT/RU2001/000550 RU0100550W WO0250845A1 WO 2002050845 A1 WO2002050845 A1 WO 2002050845A1 RU 0100550 W RU0100550 W RU 0100550W WO 0250845 A1 WO0250845 A1 WO 0250845A1
Authority
WO
WIPO (PCT)
Prior art keywords
mixture
dioxide
oxides
urine
aluminum
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.)
Ceased
Application number
PCT/RU2001/000550
Other languages
English (en)
Russian (ru)
Inventor
Feodor Grigorievich Reshetnikov
Yury Konstantinovich Bibilashvili
Oleg Vladimirovich Milovanov
Evgeny Nikolaevich Mikheev
Albert Mikhailovich Loktev
Alexandr Vladimirovich Kuleshov
Vladimir Lavrentievich Molchanov
Yury Vladimirovich Pimenov
Albert Konstantinovich Panyushkin
Alexandr Vasilievich Goloveshkin
Viktor Vasilievich Malovik
Vasily Borisovich Malygin
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.)
Federal State Unitarian Enterprise 'aabochvar All-Russia Research Institute Of Inorganic Materials'
Original Assignee
Federal State Unitarian Enterprise 'aabochvar All-Russia Research Institute Of Inorganic Materials'
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 Federal State Unitarian Enterprise 'aabochvar All-Russia Research Institute Of Inorganic Materials' filed Critical Federal State Unitarian Enterprise 'aabochvar All-Russia Research Institute Of Inorganic Materials'
Publication of WO2002050845A1 publication Critical patent/WO2002050845A1/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/006—Compounds containing uranium, with or without oxygen or hydrogen, and containing two or more other elements
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/01—Particle morphology depicted by an image
    • C01P2004/03—Particle morphology depicted by an image obtained by SEM
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/80—Compositional purity
    • 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

Definitions

  • ⁇ ⁇ slednee v ⁇ emya ⁇ ed ⁇ ini mayu ⁇ sya ⁇ yg ⁇ i ⁇ imizi ⁇ va ⁇ s ⁇ s ⁇ av and s ⁇ u ⁇ u ⁇ u ma ⁇ e ⁇ iala ⁇ able ⁇ ⁇ a ⁇ im ⁇ b ⁇ az ⁇ m, ch ⁇ by umenshi ⁇ me ⁇ aniches ⁇ e vzaim ⁇ deys ⁇ vie ⁇ livny ⁇ ⁇ able ⁇ and ⁇ b ⁇ l ⁇ ch ⁇ i and ⁇ vysi ⁇ nadezhn ⁇ s ⁇ ⁇ e ⁇ l ⁇ vydelyayuschi ⁇ sb ⁇ in usl ⁇ viya ⁇ i ⁇ ⁇ ab ⁇ y in manev ⁇ enny ⁇ ⁇ ezhima ⁇ .
  • a nuclear fuel tablet is known to contain hurricane dioxide with the addition of gadolinium oxide and aluminum silicates at a low temperature of 25 centigrade (25).
  • the quantity of aluminum-silicate in the tablets is from 0.001 to 0.05 wt.%,
  • 25 with additives have an average size of 20 to 60 microns.
  • a well-known well-known operation is a low operational reliability of the body and the operation of the heat-separating devices under conditions of maneuvering. This is, in particular, due to a relatively high height. 2
  • a nuclear test plate is known to be dead, which also includes a metallic
  • a well-known well-known operation is a low operational reliability of the body when operating in a separate mode under conditions of maneuvering. This, in particular, is due to the fact that it is 5 high temperature-sensitive and portable, and therefore does not neglect it.
  • DISCLOSURE OF EMBODIMENTS OF THE INVENTION The main purpose of the claimed invention is to increase the cost-effectiveness of the material for the consumption of waste
  • the goal is achieved by the fact that, at the first variant of the implementation of the fuel-grade fuel from uranium dioxide, it contains aluminum 0.02 to 0.10 wt.% And potassium oxide. in the country, the country is divided into the borders of the world
  • the size of the urine dioxide grain is 10 to 20 microns;
  • the tablet contains 0.3 to 10 wt. % gadolinia or ⁇ 0.3 to 0.8 wt. % erbium in the form of acid.
  • the set goal is achieved in that, by the second option
  • niobium for example, aluminum and black oxide in the form of oxides are dispersed at the borders of the grains of dioxide of uranium in the form of fusible eutectic, and niobium in the form of oxide is discharged.
  • the size of the urine dioxide grain is up to 12 to 30 microns;
  • the tablet contains 0.3 to 10 wt. % gadolinia or ⁇ 0.3 to 0.8 wt. % erbium in the form of oxides.
  • Uranium dioxide grains are in the form of fusible alloys, as well as in the form of oxides in the form of oxides, iron is also excluded, and the remaining part of the iron is in the form of an industrial waste material.
  • the size of the urine dioxide grain is 10 to 20 ⁇ m;
  • the tablet contains 0.3 to 10 wt. % gadolinia or ⁇ 0.3 to 0.8 wt. % erbium in the form of oxides.
  • the size of the urine dioxide grain is up to 12 to 30 microns;
  • Table 5 contains 0.3 to 10 wt. % gadolinia or ⁇ 0.3 to 0.8 wt. % erbium in the form of oxides.
  • the stated goal is also achieved by the fact that, in the first embodiment, the method of production of the method for producing the fuel from uranium dioxide, containing 0% of aluminum, is 0% in weight, 0% of 0%.
  • the method of production of the method for the production of fuel from uranium dioxide, containing 0% of aluminum is 0%. ⁇ 0.05 to 0.15 wt. %, In ⁇ sh ⁇ di ⁇ sida u ⁇ ana d ⁇ bavlyayu ⁇ ⁇ sh ⁇ alyum ⁇ sili ⁇ a ⁇ a Z ⁇ ⁇ 2 March 23 2 0.1 ⁇ liches ⁇ ve ⁇ d ⁇ 0.25 wt.%, 5 ⁇ y ⁇ edva ⁇ i ⁇ eln ⁇ ⁇ alivayu ⁇ on v ⁇ zdu ⁇ e ⁇ i ⁇ em ⁇ e ⁇ a ⁇ u ⁇ e ⁇ 700 C and 800 d ⁇ izmelchayu ⁇ d ⁇ ⁇ azme ⁇ a chas ⁇ its least 40 m ⁇ m and ⁇ a ⁇ zhe d ⁇ bavlyayu ⁇ ⁇ sh ⁇ ⁇ sida ni ⁇ biya
  • the set goal is also achieved, in other words, by a fourth option
  • ⁇ a ⁇ ig. 3 ⁇ ivedena ⁇ g ⁇ a ⁇ iya uchas ⁇ a ⁇ ve ⁇ n ⁇ s ⁇ i ⁇ able ⁇ (va ⁇ ian ⁇ che ⁇ y ⁇ e) in ⁇ a ⁇ a ⁇ e ⁇ is ⁇ iches ⁇ m ⁇ en ⁇ gen ⁇ vs ⁇ m radiation on ⁇ y ⁇ azan ⁇ iron ⁇ as ⁇ edelenie, v ⁇ dyascheg ⁇ in ⁇ las ⁇ i ⁇ itsi ⁇ uyuschuyu d ⁇ bav ⁇ u, ⁇ around ⁇ bemu ⁇ livny ⁇ ⁇ able ⁇ .
  • Example 1 The implementation of the method (option 1) of the receipt of the table.
  • the original hazardous oxide of uranium is sifted through vibrations with a cell size of 400 ⁇ m.
  • the fraction that went through the system, in the amount of 4300 g, is selected for the manufacture of the tablets.
  • 25 28U 2 heat up in a thermal furnace at a temperature of 750 ° C for one hour. Grind the spreading additive in the grind, sift through the purchased system with a size of 40 ⁇ m, and take out the waste. It takes 200 g of urine dioxide powder and 107.5 g of alumina silica powder (mullite)
  • an organic mix uses vinyl alcohol in an amount of 8 wt. % and glycerol in the amount of 0.5 wt.% ⁇ .
  • Luminosilicate (mullite) ⁇ 1 2 ⁇ 3 28 282 2 heat up in a thermal furnace at a temperature of 750 ° ⁇ for one hour. Grind the flaky additive to the surface, grind it through a kapron system with a mesh size of 40 ⁇ m. Fraction, ⁇ passed through
  • Niobium oxide impinges on the air at a temperature of 1200 ° C. grind in a particle, sieve through a cash system with a size of 40 microns. The fraction that has gone through the system is selected for the manufacture of the tablets. It takes 200 g of urine dioxide powder, 107.5 g of alumina silica powder - mullite ⁇ 1 2 ⁇ 3 28 ⁇ 2 (from the calculation of 0.20 wt.% ⁇
  • the resulting mixture is added in 1000 g of 5 powder of uric acid dioxide and mixed in a drum mixer for 45 minutes and at a speed of rotation of the drum 35 to 40 minutes per minute.
  • the resulting mixture in the amount of 1307.5 g, is divided into six equal proportions of 217.9 g, each mixture of this mixture is mixed with the mixture of urine dioxide, weighing 6941 g of each. 45 minutes Then all six
  • the value of the separation of the oxide of niobium in the total volume was 0.10 wt. % with a decline of an average of 0.013% by weight.
  • the resulting mixture is sieved through vibrations with a size of 400 ⁇ m cells and mixed with an organic binder.
  • an organic mix uses vinyl alcohol in an amount of 8 wt. %> and glycerol in an amount of 0 0.5 wt.%).
  • the resulting "checkers" are crushed in a mill and are sifted through a vibrator with a cell size of 630 ⁇ m.
  • the resulting process dried at 5 ° C at a temperature of 20 ° C for 24 hours.
  • the circuit boards for the bodies of the process are suitable for 5.7 - 6.0 g / cm 3 .
  • the resulting tablets are loaded into molybdenum miners and stored in a furnace with a temperature of 1750 ° C in a medium containing water.
  • EXAMPLE 3 The implementation of the method of receipt of the tablets (option 3).
  • Example 10 (a plastic additive) for a total volume of 0.063 wt. % when removed from the average in the range of 0.013 wt. >. It is prepared for use on the press, and the tablets are shipped and stored in the same way as in Example 1.
  • Example 4 Implementation of a method for receiving a tablet (option 4). Prepares the original source of urine dioxide, as in example 1. Certainly ⁇ Brass In quality
  • Niobium oxide is incinerated on the air at a temperature of 1200 ° C, it is crushed in a powder, it is sifted through a capacitive system with a cell size of 40 ⁇ m. A partition that has gone through the system is selected for the manufacture of the tablets. 200 g of urine dioxide by-product, 45 g of powder by-product and 43 g of 5 niobium oxide powder are mixed in a drum mixer for 45 minutes of the by-product being consumed for 40 minutes. Mixes the obtained mixture with the rest of the powder of uricane, as in Example 1. Of the upper, lower, and middle parts of the obtained mixture, it is useful for analyzing
  • Example 5 Implementation of a method for receiving a tablet (option 1 with gadolinium).
  • uroxidic oxide As in Example 1.
  • the gadolinium oxide is excipient, it is screened through a system with a cell size of 100 ⁇ m. The fraction, 5 which came through the system, is taken to make the tablets.
  • the powder of uronic oxide in the amount of 43,000 g and the bulk of the oxide of gadolinium in the amount of 2150 g are mixed in a vacuum mixer for 3 minutes. The resulting mixture is mixed with alumina silicate in accordance with procedure 1. It is supplied to a
  • Example 6 The implementation of the method of radiation of the tablets (option 1 with erbium).
  • Erosium oxide is sieved through a cell with a cell size of 15. A fraction that has gone through the system is taken to make the tablets.
  • the powder of uric oxide in a quantity of 200 g, 107.5 g of powder of aluminum silicate and 250 g of powder of erbium oxide is mixed in a drum mixer for 45 minutes, the product is supplied with steam. The obtained mixture is mixed with the basic part of the powder of the uranium for the first time in combination with the product.
  • the preparation of research tests and the conduct of research and their properties were carried out using well-known methods.
  • the mass fraction of iron, silver, aluminum, and niobium was divided by the specific 25 and chemical methods, the parameters of the industrial methods were shared with the industrial methods.
  • the commercial tests for the separation of the plastic table were divided by model 1246- ⁇ -2 / 2300-1 on a machine and a temperature of 20 to 900 ° C in vacuum.
  • the separation of the phasic equipment was carried out by the X-ray method in the camera of the KC-86 type on the basis of cosmic radiation.
  • the distribution of alloying additives in sintered tablets from urine dioxide was divided with the use of a microanalysis of c-radiation for the generation of radiation.
  • the separation of the alloying elements in the inventive table is indicated by the fact that the aluminum and brown compounds correspond to the mixture entered into the mixture.
  • the analysis of the microprocesses showed that aluminum and aluminum oxide in the form of oxides are used to reduce the fusion of euthanic oxide at 5 boundaries of igranium dioxide 2 (see.
  • niobium in the form of an oxide (5) is included in the composition of a separate oxidized oxide and is usable.
  • the other part of the iron in the form of the oxide is treated with the dioxide of the solid solution and the same is divided into the size of the table.
  • P ⁇ vyshenie ⁇ las ⁇ ichn ⁇ s ⁇ i ma ⁇ e ⁇ iala yade ⁇ n ⁇ g ⁇ ⁇ liva ⁇ i ⁇ ab ⁇ chi ⁇ 5 ⁇ em ⁇ e ⁇ a ⁇ u ⁇ a ⁇ eg ⁇ is ⁇ lz ⁇ vaniya ⁇ zv ⁇ li ⁇ susches ⁇ venn ⁇ snizi ⁇ me ⁇ aniches ⁇ e vzaim ⁇ deys ⁇ vie s ⁇ lba ⁇ livny ⁇ ⁇ able ⁇ with ⁇ b ⁇ l ⁇ ch ⁇ y ⁇ vela, ⁇ s ⁇ benn ⁇ ⁇ i ⁇ ab ⁇ e a ⁇ mny ⁇ s ⁇ antsy in manev ⁇ enny ⁇ ⁇ ezhima ⁇ .
  • the method is given in the table.

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  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Geology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Inorganic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Ceramic Engineering (AREA)
  • Pharmaceuticals Containing Other Organic And Inorganic Compounds (AREA)
  • Compositions Of Oxide Ceramics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

L'invention relève du cycle de combustible en industrie énergétique nucléaire et notamment de la composition d'une pastille de combustible nucléaire à base de dioxyde d'uranium ainsi que d'un procédé de fabrication de cette pastille. L'invention peut s'utiliser pour augmenter la plasticité du combustible nucléaire et réduire l'interaction entre une colonne de pastilles de carburant et une enveloppe d'élément combustible pendant l'utilisation. Selon l'invention, la pastille de combustible nucléaire à base de dioxyde d'uranium contient de 0,03 à 0,10 % en masse d'aluminium et de 0,01 à 0,05 % en masse de silicium. L'aluminium et le silicium sous la forme d'oxydes sont répartis le long de la frontière des grains de dioxyde d'uranium, sous une forme eutectique à point de fusion bas. En outre, elle peut contenir de 0,05 à 0,15 % en masse de niobium, de 0,04 à 0,15 % en masse de fer, et une partie du fer se présentant comme des oxydes forme une solution solide avec le matériau de dioxyde d'uranium. L'invention concerne aussi cinq procédés de fabrication de combustible nucléaire.
PCT/RU2001/000550 2000-12-18 2001-12-17 Pastille de combustible nucleaire et procede de fabrication Ceased WO2002050845A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2000131713 2000-12-18
RU2000131713/06A RU2193242C2 (ru) 2000-12-18 2000-12-18 Таблетка ядерного топлива

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WO2002050845A1 true WO2002050845A1 (fr) 2002-06-27

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WO (1) WO2002050845A1 (fr)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2268507C2 (ru) * 2003-04-04 2006-01-20 Открытое акционерное общество "Ульбинский металлургический завод" Таблетка ядерного керамического топлива с регулируемой микроструктурой
FR2853759B1 (fr) * 2003-04-09 2005-05-13 Commissariat Energie Atomique Combustible nucleaire a fils tresses et son procede de realisation
RU2339094C2 (ru) * 2004-10-06 2008-11-20 Акционерное общество "Ульбинский металлургический завод" Таблетка ядерного уран-эрбиевого керамического топлива
RU2423742C1 (ru) * 2010-03-09 2011-07-10 Открытое акционерное общество "Машиностроительный завод" Способ изготовления таблеток ядерного топлива с регулируемой микроструктурой
RU2760902C1 (ru) * 2021-05-11 2021-12-01 Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Сплав на основе урана (варианты)

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4869866A (en) * 1987-11-20 1989-09-26 General Electric Company Nuclear fuel
US5257298A (en) * 1991-03-04 1993-10-26 Nippon Nuclear Fuel Development Co., Ltd. Nuclear fuel pellets having an aluminosilicate deposition phase
RU2065627C1 (ru) * 1995-04-20 1996-08-20 Научно-исследовательский и конструкторский институт энерготехники Тепловыделяющая сборка канального ядерного реактора
RU2081063C1 (ru) * 1989-12-05 1997-06-10 Компани Женераль де Матьер Нюклеэр Способ получения топливных урановых таблеток (варианты)
RU2093468C1 (ru) * 1995-12-09 1997-10-20 Сибирский химический комбинат Способ получения диоксида урана или оксидной композиции на его основе
RU2157568C1 (ru) * 1999-11-26 2000-10-10 Открытое акционерное общество "Машиностроительный завод" Таблетка ядерного топлива

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2142170C1 (ru) * 1998-02-18 1999-11-27 ОАО "Машиностроительный завод" Таблетка ядерного топлива

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4869866A (en) * 1987-11-20 1989-09-26 General Electric Company Nuclear fuel
RU2081063C1 (ru) * 1989-12-05 1997-06-10 Компани Женераль де Матьер Нюклеэр Способ получения топливных урановых таблеток (варианты)
US5257298A (en) * 1991-03-04 1993-10-26 Nippon Nuclear Fuel Development Co., Ltd. Nuclear fuel pellets having an aluminosilicate deposition phase
RU2065627C1 (ru) * 1995-04-20 1996-08-20 Научно-исследовательский и конструкторский институт энерготехники Тепловыделяющая сборка канального ядерного реактора
RU2093468C1 (ru) * 1995-12-09 1997-10-20 Сибирский химический комбинат Способ получения диоксида урана или оксидной композиции на его основе
RU2157568C1 (ru) * 1999-11-26 2000-10-10 Открытое акционерное общество "Машиностроительный завод" Таблетка ядерного топлива

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