EP2797082B1 - Verfahren zum aufarbeiten fester radioaktiver abfälle - Google Patents

Verfahren zum aufarbeiten fester radioaktiver abfälle Download PDF

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Publication number
EP2797082B1
EP2797082B1 EP12860442.8A EP12860442A EP2797082B1 EP 2797082 B1 EP2797082 B1 EP 2797082B1 EP 12860442 A EP12860442 A EP 12860442A EP 2797082 B1 EP2797082 B1 EP 2797082B1
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EP
European Patent Office
Prior art keywords
waste
slag
melting
retreatment
radioactive waste
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Application number
EP12860442.8A
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English (en)
French (fr)
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EP2797082A1 (de
EP2797082A4 (de
Inventor
Anatolij Anatoljevich Golubev
Jurij Alexandrovich Gudim
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Obchestvo S Ogranichennoj Otvetstvennostju Promishlennaja Kompanija "Tehnologija Metallov"
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Obchestvo S Ogranichennoj Otvetstvennostju Promishlennaja Kompanija "Tehnologija Metallov"
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Publication of EP2797082A4 publication Critical patent/EP2797082A4/de
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G21F9/308—Processing by melting the waste

Definitions

  • the present invention relates to the field of environment control and to the field of retreatment of solid waste contaminated with radionuclides.
  • solid radioactive waste In the course of the service, repairs and removal from service of nuclear power and other plants, solid radioactive waste (SRW) is formed and accumulated.
  • waste comprises: filters, sorbents, ion-exchange resins, products of hardening liquid radioactive waste, elements of technological equipment, of biological shielding, pipe-lines, tools, building structures, working clothes, heat insulation, etc.
  • solid radioactive waste is subdivided into:
  • the known process and device for retreating solid radioactive waste provide for adding, before the compressing step, aluminosilicates and some flux into said solid radioactive waste, said flux forming an eutectic mixture with the melt ashes, combining together the drying and pyrolysis areas to have in this combined area an initial temperature of 350°C and a final temperature of 600°C, dividing the combustion area into a precombustion area with an initial temperature of 600°C and a final temperature of 800°C and an afterburning area with an initial temperature of 1200°C, the products of the thermal processing of the solid radioactive waste with said aluminosilicates and said flux being conveyed, after the drying and pyrolysis areas, through the precombustion area, and then, by gravity, through a gasification area with an initial temperature of 800°C and a final temperature of 1200°C with simultaneous supply of water vapor into the same, through the afterburning area, the drying area and the pyrolysis area, the gasification area being submitted to a forced
  • An object of the claimed process for the retreatment of solid radioactive waste is to improve the technical and economic performance of the retreatment process and the ecological security level.
  • the waste to be processed is submitted to preliminary heating in a preheater by the heat of outgoing gases having a temperature of 1600-1750°C, the heated solid radioactive waste is loaded into the melting chamber with the help of an air-tight device via an opening in a side wall of the chamber at a rate of 0.8 to 1.1 tons per hour for 1 m 2 of the liquid melt, the waste fusion is carried out continuously in a fuel-oxygen slag-lining melting chamber, the outgoing gases from the last being channeled into the preheater, during the waste retreatment process, a constant level of liquid metal is maintained in the lined molten-metal pool of the chamber, the "dirty" radioactive slag from the melting chamber is discharged at the melting section after accumulating a slag layer 250
  • the melting chamber housing is cooled with a liquid-metal heat-transfer agent.
  • the pouring-off of the "dirty" radioactive slag is carried out at the radiation-contaminated melting section into containers for waste burial, mounted on a conveyor.
  • the temperature of outgoing gases issued from the preheater is maintained at the level 700-850°C, then these gases are quickly cooled down to 200°C to provide "quenching" of the same.
  • the gases outgoing from the melting chamber are treated to remove dust in a dust purifier, the dust trapped from the gases being packed and put onto the bottom of the containers before filling the same with radioactive slag, the slag being finally poured inside from above.
  • the gases outgoing from the melting chamber are purified in a gas-purifying unit, the dust trapped from the gases being blown into the containers by an injector while filling the same with slag.
  • loading of preheated radioactive waste into the melting chamber is carried out while maintaining a preset height of the molten slag layer and at a constant level of melted metal in the molten metal pool.
  • Carrying out continuously the process for retreating solid radioactive waste in a fuel-oxygen slag-lining melting chamber enables to increase the output of the process, to reduce the consumption of heat-transfer agent, to significantly reduce as well the irradiation of the staff, to reduce the evaporation of volatile radionuclides and to reduce the amount of radioactive waste by-products formed due to the absence of refractory lining in the slag area and in the free space of the melting chamber.
  • Preheating of solid radioactive waste in a preheater by the gases outgoing from the melting chamber with a temperature of 1600-1750°C enables to reduce the heat-transfer agent consumption for the waste retreating process, to accelerate melting of the waste and to increase the output of the process of retreating the same.
  • the preheater is located at the side of the melting chamber which enables to ease up loading of solid radioactive waste into the same. At the same time, the overall size of the production room is reduced which enables to decrease capital outlays to build the shop.
  • Loading of preheated solid radioactive waste with an air-tight device via an opening in a side wall of the melting chamber at a rate of 0.8-1.2 tons per hour per square meter of liquid melt area provides for optimal conditions to process solid radioactive waste in the melting chamber.
  • the hermetically sealed device prevents radioactive bursts into the working space of the fusion section which reduces irradiation of the staff in the "dirty" section of the production room.
  • Loading of preheated solid radioactive waste at a rate of 0.8-1.1 tons per hour per square meter of liquid melt area provides for the maximum rate of waste burning and melting and for a high output of the retreatment process.
  • the rate of loading the preheated solid radioactive waste of 1.1 tons per hour per square meter of liquid melt surface is hard to provide at a low density of the waste (for example, in the case of rock thermal insulation). Besides, at such a loading rate, the loaded waste has no time to be completely melted.
  • Performing loading, preheating, fusion and running-off of "dirty" radioactive slag at a "dirty”, radiation-contaminated melting section isolated by a closed partition or a wall from a "clean" section of casting metal obtained in the melting chamber provides for a high-capacity operation of the melting chamber and isolates the hazardous site, which reduces irradiation of the production staff.
  • Casting the metal obtained in the melting chamber at a section isolated from the melting section by a closed partition of a wall additionally isolates the hazardous section, which reduces the irradiation of the production staff.
  • Dividing the production room where a melting chamber is located with a closed partition or a wall into a "clean" and a "dirty” sections enables to carry out the waste loading into a preheater without any additional irradiation of the staff and to keep the stocks of solid radioactive waste in the "dirty" section of the shop.
  • Loading waste through an opening in the side wall of the melting chamber reduces the entrainment of waste particles with the outgoing gases from the working space of the chamber.
  • the temperature of the gases outgoing from the charge preheater in the range of 700-850°C and successive chilling of the same to 200°C enable to exclude the formation of dioxins while heating and reprocessing the solid radioactive waste containing PVC-type plastics and to prevent resynthesis (a new synthesis) of dioxins while chilling outgoing gases in the temperature range of 700°C-200°C.
  • the process for the retreatment of solid radioactive waste is carried out as follows.
  • a melting chamber 1 is charged, in small portions, with low-melting waste of ferrous metals: cast iron and steel chips, pig iron, small-sized steel waste ends, and fuel-oxygen burners 2 fuse metal 3 to a liquid state in an amount necessary to fill the maximum volume of a lined molten metal pool.
  • solid radioactive waste 4 situated at a "dirty" melting section of the shop, contaminated with radiation is charged into a preheater 5 situated at the side of the melting chamber 1, where it is preheated using the heat of gases outgoing from the melting chamber 1 and having a temperature of 1600-1750°C.
  • the heated solid radioactive waste is loaded with an air-tight device from the preheater 5 to the melting chamber 1 through an opening in a side wall of the melting chamber at a rate of 0.8-1.1 tons per hour per 1 m 2 of the molten metal surface. Burning and fusing of the loaded waste 4 are performed on the surface of the liquid molten metal obtained in the waste retreating, or inside the same. During the solid radioactive waste retreating process, a constant level of liquid metal 3 is maintained in the lined molten metal pool of the chamber 1, not lower than the upper limit of the same.
  • the "dirty” slag is poured-off into a container 8 via a slag trough 9 from the melting chamber 1 at the "dirty", radiation-contaminated melting section separated by a closed partition 13 or a wall 13 from a "clean" section for casting the metal obtained in the melting chamber 1.
  • the "clean" metal is poured from the melting chamber 1 via a long trough 10 at the "clean” section of the shop into a pouring ladle 11 through a metal tap hole 12.
  • the solid radioactive waste is retreated in a slag lined fuel-oxygen melting chamber the housing of which is cooled by a liquid metal heat-transfer agent.
  • the temperature of the gases outgoing from the preheater 5 is kept in the range of 700-850°C and after that, the gases are chilled rapidly to 200°C to exclude the formation of dioxins while reprocessing waste containing plastics and to prevent resynthesis of dioxins while the gases are cooled slowly.
  • the dust trapped in a gas purifier (not shown in the Figure) is placed in a particular package onto the bottom of the containers 8 or barrels 8 before filling the same with liquid radioactive slag, the last being poured to fill them and to embed it in the body of the slag ingot enclosed in the container or the barrel.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)
  • Gasification And Melting Of Waste (AREA)

Claims (11)

  1. Verfahren zur Folgebehandlung von festen radioaktiven Abfall, umfassend die Schritte
    Abfallbeladung,
    Verhütten,
    getrennter Abstich von Schlacke und Metall und Produkten der Folgebehandlung aus einer Schmelzkammer,
    wobei der zur Folgebehandlung vorgesehene Abfall einer Vorerhitzung in einem Vorerhitzer durch Wärme von Gasen zugeführt wird, welche aus der Schmelzkammer mit einer Temperatur von 1600-1750°C abgehen,
    der erhitzte feste radioaktive Abfall wird in die Schmelzkammer mittels einer luftdichten Vorrichtung mit einer Geschwindigkeit von 0,8-1,1 Tonnen pro Stunde pro 1 m2 Flüssigschmelzoberfläche durch eine Öffnung in der Seitenwand der Kammer zugeführt,
    die Abfallverhütung wird kontinuierlich in einer Brennstoff-Sauerstoff-Schlackenauskleidung-Schmelzkammer durchgeführt,
    die aus derselben abgehenden Gase werden zum Vorerhitzer geleitet,
    während des Verfahrens der Abfallfolgebehandlung wird ein konstantes Niveau an flüssigem Metall in dem ausgekleideten Metallbecken der Kammer aufrechterhalten,
    das Abgießen von "schmutziger" radioaktiver Schlacke aus der Schmelzkammer erfolgt im Schmelzabschnitt nachdem sich eine 250-400 mm hohe Schlackenschicht an der Oberfläche der Metallschmelze angesammelt hat, das in der Schmelzkammer erhaltene Metall wird an einer Stelle abgegossen, die von dem Schmelzabschnitt durch eine geschlossene Trennwand separiert ist.
  2. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei das Gehäuse der Schmelzkammer während der Folgebehandlung des festen radioaktiven Abfalls mit einem Flüssigmetall-Wärmeübertragungsmittel gekühlt wird.
  3. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die Schritte der Beladung, des Vorwärmens, der Verhüttung und des Abgießens von "schmutziger" radioaktiver Schlacke in einem "schmutzigen", durch Strahlung kontaminierten und durch eine geschlossene Trennwand von einem "sauberen" Abschnitt zum Abgießen des in der Schmelzkammer erhaltenen Metalls separierten, Schmelzabschnitt durchgeführt wird.
  4. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die Schritte der Beladung, des Vorwärmens, der Verhüttung und des Abgießens von "schmutziger" radioaktiver Schlacke in einem "schmutzigen", durch Strahlung kontaminierten und durch eine Wand von einem "sauberen" Abschnitt zum Abgießen des in der Schmelzkammer erhaltenen Metalls separierten, Schmelzabschnitt durchgeführt wird.
  5. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei das Abgießen der "schmutzigen" radioaktiven Schlacke in einem radioaktiv kontaminierten Schmelzabschnitt in auf einem Förderband befestigte Deponieabfallbehälter erfolgt.
  6. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die Temperatur der aus dem Vorerhitzer ausgehenden Gase auf einem Niveau von 700-850°C gehalten wird, dann werden diese Gase schnell auf 200°C abgekühlt um eine "Abschreckung" zu bewirken.
  7. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die aus der Schmelzkammer abgehenden Gase behandelt werden um Staub in einem Staubreiniger zu entfernen, und der von den Gasen abgefangene Staub wird verpackt und auf dem Boden der Behälter abgelegt bevor diese mit flüssiger radioaktiver Schlacke befüllt werden, wobei die Schlacke in deren Inneres letztendlich gegossen wird.
  8. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die aus der Schmelzkammer abgehenden Gase in einer Gasreinigungseinheit gereinigt werden und der von den Gasen abgefangene Staub durch eine Einspritzvorrichtung in die Behälter geblasen wird während diese mit Schlacke befüllt werden.
  9. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die Verbrennung und Schmelzung des zugeführten Abfalls auf der Oberfläche der Flüssigschmelze erfolgt während der Abfall folgebehandelt wird.
  10. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die Verbrennung und Schmelzung des zugeführten Abfalls im Inneren der Flüssigschmelze erfolgt während der Abfall folgebehandelt wird.
  11. Verfahren zur Folgebehandlung von festen radioaktiven Abfall nach Anspruch 1, wobei die Zuführung des vorgewärmten radioaktiven Abfalls in die Schmelzkammer erfolgt während eine vorgegebene Höhe der geschmolzenen Schlackenschicht und ein konstantes Niveau des geschmolzenen Metalls in dem Schmelzmetallbad gehalten wird.
EP12860442.8A 2011-12-23 2012-12-17 Verfahren zum aufarbeiten fester radioaktiver abfälle Active EP2797082B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2011152899/07A RU2486616C1 (ru) 2011-12-23 2011-12-23 Способ переработки твердых радиоактивных отходов
PCT/RU2012/001075 WO2013095197A1 (ru) 2011-12-23 2012-12-17 Способ переработки твердых радиоактивных отходов

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EP2797082A1 EP2797082A1 (de) 2014-10-29
EP2797082A4 EP2797082A4 (de) 2015-09-02
EP2797082B1 true EP2797082B1 (de) 2016-10-26

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WO2017014666A1 (ru) * 2015-07-23 2017-01-26 Общество С Ограниченной Ответственностью Промышленная Компания "Технология Металлов" Способ подготовки радиоактивной пыли к длительному хранению или захоронению и устройство для его осуществления
RU2667149C1 (ru) * 2017-12-06 2018-09-17 Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" (Ао "Концерн Росэнергоатом") Установка для переработки радиоактивных отходов
RU2686056C1 (ru) * 2018-10-08 2019-04-24 Юрий Петрович Благодаров Способ обеззараживания радиоактивных отходов органического происхождения
RU2722585C1 (ru) * 2019-07-15 2020-06-01 Амир Нурутдинович Хуснутдинов Способ фрагментации металлической конструкции и плавящий модуль
CN115831426B (zh) * 2022-11-16 2024-03-22 中国原子能科学研究院 放射性物质的处理装置和处理方法

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DE19546789A1 (de) * 1995-12-14 1997-06-19 Siemens Ag Verfahren zur Verwertung kontaminierter Metallteile
JP2989555B2 (ja) * 1996-11-22 1999-12-13 核燃料サイクル開発機構 放射性固体廃棄物の溶融処理方法
RU2123214C1 (ru) 1997-12-03 1998-12-10 Московское государственное предприятие - объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды Способ переработки твердых радиоактивных отходов
RU2140109C1 (ru) 1998-09-03 1999-10-20 Московское государственное предприятие - объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды (Мос. НПО. "Радон") Способ и устройство для переработки твердых радиоактивных отходов
RU2157570C1 (ru) 1999-07-14 2000-10-10 Московское государственное предприятие Объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды Плазменная шахтная печь для переработки твердых радиоактивных и токсичных отходов
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RU2486616C1 (ru) 2013-06-27
EP2797082A1 (de) 2014-10-29
EP2797082A4 (de) 2015-09-02
WO2013095197A1 (ru) 2013-06-27

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