EP2797082B1 - Procédé de transformation de déchets radioactifs solides - Google Patents

Procédé de transformation de déchets radioactifs solides 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
Prior art date
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Application number
EP12860442.8A
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German (de)
English (en)
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EP2797082A4 (fr
EP2797082A1 (fr
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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    • 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)
  • Gasification And Melting Of Waste (AREA)
  • Processing Of Solid Wastes (AREA)

Claims (11)

  1. Procédé pour le retraitement de déchets radioactifs solides, comprenant les étapes consistant à :
    charger des déchets,
    les mettre en fusion,
    prélever séparément le laitier et le métal, produits du retraitement, depuis une chambre de fusion,
    dans lequel les déchets à retraiter sont soumis à un chauffage préalable dans un réchauffeur par la chaleur des gaz sortant de la chambre de fusion à une température de 1600 à 1750° C,
    les déchets radioactifs solides chauffés sont chargés dans la chambre de fusion avec l'aide d'un dispositif étanche à l'air via une ouverture dans une paroi latérale de la chambre, à un débit de 0,8 à 1,1 t par heure et par mètre carré de la surface de fusion du liquide,
    la mise en fusion des déchets est effectuée en continu dans une chambre de fusion carburant/oxygène à garniture de laitier,
    les gaz sortant provenant de celle-ci sont menés au préchauffeur via un canal,
    un niveau constant de métal liquide dans le bain de métal garni de la chambre est maintenu pendant le processus de retraitement des déchets,
    déverser du laitier radioactif "pollué" hors de la chambre de fusion, effectué au niveau de la section de fusion après accumulation d'une couche de laitier de 250 à 400 mm de hauteur sur la surface du métal en fusion, la coulée du métal obtenu dans la chambre de fusion étant exécutée au niveau d'un site séparé de la section de fusion par une cloison fermée.
  2. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel pendant le retraitement des déchets radioactifs solides, le boîtier de la chambre de fusion est refroidi avec un agent de transfert thermique liquide/métal.
  3. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel les étapes de chargement, de préchauffage, de fusion et de déversement du laitier radioactif "pollué" sont effectuées au niveau d'une section de fusion "polluée", contaminée par radiation et séparée par une cloison fermée vis-à-vis d'une section "propre" pour couler le métal obtenu dans la chambre de fusion.
  4. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel les étapes de chargement, de préchauffage, de fusion et de déversement du laitier radioactif "pollué" sont effectuées au niveau d'une section de fusion "polluée", contaminée par radiation et séparée par une paroi vis-à-vis d'une section "propre" pour couler le métal obtenu dans la chambre de fusion.
  5. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel la décharge du laitier radioactif "pollué" est effectuée au niveau de la section de fusion contaminée par radiation vers des conteneurs pour enterrer les déchets, montés sur un convoyeur.
  6. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel la température des gaz sortants provenant du préchauffeur est maintenue au niveau de 700 à 850° C, puis ces gaz sont rapidement refroidis jusqu'à 200° C pour assurer une "trempe" de ceux-ci.
  7. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel les gaz sortant de la chambre de fusion sont traités pour supprimer les poussières dans un purificateur à poussière, et les poussières piégées hors des gaz sont emballées et placées sur le fond des conteneurs avant de remplir ceux-ci avec le laitier radioactif liquide, le laitier étant finalement versé à l'intérieur de ces conteneurs.
  8. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel les gaz sortant de la chambre de fusion sont purifiés dans une unité de purification de gaz, les poussières piégées hors des gaz étant soufflées dans les conteneurs par un injecteur tout en remplissant ces conteneurs avec le laitier.
  9. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel le brûlage et la fusion des déchets chargés sont effectués sur la surface du liquide en fusion tout en retraitant les déchets.
  10. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel le brûlage et la fusion des déchets chargés sont effectués à l'intérieur du liquide en fusion tout en retraitant les déchets.
  11. Procédé pour le retraitement de déchets radioactifs solides selon la revendication 1, dans lequel le chargement des déchets radioactifs préchauffés dans la chambre de fusion est effectué tout en maintenant une hauteur préétablie de la couche de laitier en fusion et à un niveau constant de métal en fusion dans le bain de métal en fusion.
EP12860442.8A 2011-12-23 2012-12-17 Procédé de transformation de déchets radioactifs solides Active EP2797082B1 (fr)

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 (fr) 2011-12-23 2012-12-17 Procédé de transformation de déchets radioactifs solides

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

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WO2017014666A1 (fr) * 2015-07-23 2017-01-26 Общество С Ограниченной Ответственностью Промышленная Компания "Технология Металлов" Procédé de préparation de la poussière radioactive au stockage durable ou à l'ensevelissement et dispositif pour sa mise en oeuvre
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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Publication number Publication date
RU2486616C1 (ru) 2013-06-27
EP2797082A4 (fr) 2015-09-02
WO2013095197A1 (fr) 2013-06-27
EP2797082A1 (fr) 2014-10-29

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