WO2017131557A1 - Procédé de conditionnement de déchets radioactifs liquides - Google Patents

Procédé de conditionnement de déchets radioactifs liquides Download PDF

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Publication number
WO2017131557A1
WO2017131557A1 PCT/RU2017/000036 RU2017000036W WO2017131557A1 WO 2017131557 A1 WO2017131557 A1 WO 2017131557A1 RU 2017000036 W RU2017000036 W RU 2017000036W WO 2017131557 A1 WO2017131557 A1 WO 2017131557A1
Authority
WO
WIPO (PCT)
Prior art keywords
radioactive waste
container
cement
liquid radioactive
lrw
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/RU2017/000036
Other languages
English (en)
Russian (ru)
Inventor
Виктор Павлович РЕМЕЗ
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.)
Eksorb Ltd
Original Assignee
Eksorb Ltd
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 Eksorb Ltd filed Critical Eksorb Ltd
Priority to EA201800446A priority Critical patent/EA201800446A1/ru
Publication of WO2017131557A1 publication Critical patent/WO2017131557A1/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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Classifications

    • 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
    • G21F9/04—Treating liquids
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • G21F9/165—Cement or cement-like matrix

Definitions

  • the invention relates to technologies for cementing materials with radioactive components and can be used in the processing of liquid radioactive waste (LRW) accumulated and generated during the operation of nuclear power plants and other nuclear cycle facilities.
  • LFW liquid radioactive waste
  • the installation comprises a protective chamber equipped with a lock compartment, a container, a container for dry cement with additives and a cement compound preparation unit located in the protective chamber, including a container for liquid radioactive waste with a device for supplying liquid radioactive waste to the container and a mixing device connected to the rotation drive and return - translational movement "up and down", while the rails passing through the airlock compartment and ending on the outside of the protective amers, and the container is mounted on rails with the possibility of entering the protective chamber through the lock compartment, the installation is equipped with a cement dough preparation unit located outside the protective chamber, including a container for dry cement, a water tank and an additional mixing device connected to an additional rotation drive and return translational movement "up and down", while the site of preparation of the cement compound is located above the container stop in the protective chamber with the possibility of interaction I am with the container, and the cement dough preparation unit is located above
  • Installation works as follows.
  • the cart with the container is in the "clean zone”.
  • the mixers are driven into rotation and translational movement “down” to enter the container, which serves cement with additives and water in a predetermined ratio.
  • the components are mixed until a homogeneous mixture - cement paste.
  • Mixers return "up” to a starting position.
  • the airlock is opened, and the trolley, moving along the rails, enters the protective chamber.
  • LRW is supplied to the container with cement dough. Mixing takes place in the container until the composition of the cement compound is uniform.
  • the container is removed from the protective chamber to solidify the compound and finally transported to storage.
  • a known method of cementing liquid radioactive waste comprising dosing portions of the components of the cement compound into a container mounted on a trolley, mixing the cement compound using an agitator mounted in the container, which is rotationally driven by the electric drive when the container is docked with the loading unit, followed by undocking of the container with the loading unit, closing the container with the cement compound and stirrer lid and transporting it to the storage, ichayuschiysya in that the container after it is docking with a loading unit mounted sensors of the lower and upper levels, which correspond to the length depending on the salinity of liquid radioactive waste volume of liquid radioactive waste and volume cement compound; using the lower level sensor, the achievement of the set value of the volume of liquid radioactive waste in the container is recorded, after which the flow of liquid radioactive waste into the container is stopped and the flow of cement and mixing of the cement compound are started; using the upper level sensor, the achievement of the set value of the volume of the cement compound is recorded,
  • Also known is a method of cementing liquid radioactive waste (patent j sRU2309472 dated 04/03/2006), characterized in that liquid radioactive waste is supplied to the container, their level is measured, liquid radioactive waste is mixed into the container, a calculated volume of gas from an external source is supplied to the container, and unloaded liquid radioactive waste into the measuring device through an unloading tube, measuring their level in the measuring device, mixing the contents of the measuring device, unloading the liquid radioactive waste from the measuring device, increasing the pressure from an external gas source in it, container through the tube to discharge, fed to a cement container containing additives, each portion of the compound was stirred in a container.
  • Device for the method of cementing liquid radioactive waste contains a mixing unit consisting of a tank with a mixer, a drain device, a vortex device, the input of which is connected to the output of the tank with a mixer, and the output with a drain device, a pipeline for supplying LRW, a hopper for cement, bunkers for solid additives, feeders, cement dispensers and solid additives, each of which consists of a jet pump connected in series to cement and solid waste bins, a pipeline, a feed hopper, and dispensers connected to the inlet of the tank with a mixer, a circulation line equipped with a pump and connected to the inlet of the tank with a mixer.
  • the task of the invention is to remedy the above disadvantages.
  • the technical result of the claimed invention is to reduce the dose to the staff in the process of conditioning liquid radioactive waste, simplifying the technology for conditioning liquid radioactive waste, improving the reliability and safety of the process for conditioning liquid radioactive waste.
  • a method for conditioning liquid radioactive waste including supplying liquid radioactive waste to a container for cementing LRW, supplying cement with additives to a container for cementing LRW, mixing cement with additives and liquid radioactive waste until complete homogenization, wherein cement with additives is supplied in a container for cementing LRW in a package made of water-soluble materials.
  • the packaging may be made of a water-soluble polymer film, in particular polyvinyl alcohol.
  • the packaging dissolves in an aqueous medium, and the cement compound is mixed until completely homogenized, after which the container, with the mixture already cured, is sent for storage.
  • Mixing of the cement compound is carried out by means of an agitator installed in the cementing container of LRW, which is rotationally driven by an electric drive.
  • the cementing container for LRW can be placed in a protective concrete block. These concrete blocks are the end result of LRW processing and can be sent for burial or used as structural materials for the construction of storage facilities.
  • NZK-1 non-returnable protective container
  • 1.0 tons of dry cement in polyvinyl alcohol packages (20 packages of 50 kg each)
  • 100 kg of bentonite clay in polyvinyl alcohol packages (2 packages of 50 each) were placed kg)
  • 0.66 m 3 LRW with a salinity of 230 g / l and cesium activity of 137 10 7 Bq / l.
  • the cement compound was mixed for 1 hour until complete homogenization.
  • the cured cement compound in the cementing container was sent for disposal.
  • the claimed invention allows to reduce the dose load on the staff in the process of conditioning liquid radioactive waste and significantly simplify the process of conditioning liquid radioactive waste.

Landscapes

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

Abstract

L'invention concerne des techniques de cimentation de matériaux avec des composants radioactifs et peut être utilisée dans le processus de traitement de déchets liquides radioactifs (DRL) qui s'accumulent et se forment lors de l'exploitation d'une centrale nucléaire ou sur d'autres sites du cycle nucléaire. Le résultat technique de l'invention consiste à réduire les doses reçues par le personnel pendant le conditionnement des déchets radioactifs liquides, de simplifier la technologie de conditionnement des déchets radioactifs liquides et d'assurer de meilleures fiabilité et sécurité du processus de conditionnement des déchets radioactifs liquides. A cette fin, l'invention concerne un procédé de conditionnement de déchets radioactifs liquides lequel consiste à acheminer les déchets radioactifs liquides dans un conteneur de cimentation de DRL, alimenter le conteneur de cimentation de DRL avec du ciment comportant des additifs, effectuer le mélange du ciment comportant des additifs et des déchets radioactifs liquides jusqu'à un état complètement homogène, le ciment avec des additifs étant acheminé dans le conteneur pour cimenter les DRL dans l'emballage fait à partir de matériaux solubles dans le milieux aqueux.
PCT/RU2017/000036 2016-01-28 2017-01-27 Procédé de conditionnement de déchets radioactifs liquides Ceased WO2017131557A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
EA201800446A EA201800446A1 (ru) 2016-01-28 2017-01-27 Способ кондиционирования жидких радиоактивных отходов

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2016102930A RU2617113C1 (ru) 2016-01-28 2016-01-28 Способ кондиционирования жидких радиоактивных отходов
RU2016102930 2016-01-28

Publications (1)

Publication Number Publication Date
WO2017131557A1 true WO2017131557A1 (fr) 2017-08-03

Family

ID=58643035

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/RU2017/000036 Ceased WO2017131557A1 (fr) 2016-01-28 2017-01-27 Procédé de conditionnement de déchets radioactifs liquides

Country Status (3)

Country Link
EA (1) EA201800446A1 (fr)
RU (1) RU2617113C1 (fr)
WO (1) WO2017131557A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2854694C1 (ru) * 2025-08-12 2026-01-15 Акционерное общество "Научно-исследовательский и конструкторский институт монтажной технологии - Атомстрой" (АО "НИКИМТ-Атомстрой") Способ переработки жидких радиоактивных отходов

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4652404A (en) * 1983-12-01 1987-03-24 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Process for conditioning contaminated waste through cementing
RU2132095C1 (ru) * 1997-12-03 1999-06-20 Московское государственное предприятие Объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды Устройство для цементирования жидких радиоактивных отходов

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2720342B2 (de) * 1977-05-06 1979-08-30 Steag Kernenergie Gmbh, 4300 Essen Verfahren und Anlage zum Verfestigen von pumpfähigen radioaktiven Abfällen in einem Deponiebehälter
GB8423170D0 (en) * 1984-09-13 1984-11-07 Atomic Energy Authority Uk Waste immobilisation
SU1338697A1 (ru) * 1985-07-03 1996-03-20 В.И. Кольба Способ отверждения жидких радиоактивных отходов
EP3160533B1 (fr) * 2014-06-24 2020-08-12 Medtronic Inc. Poche de sorbant

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4652404A (en) * 1983-12-01 1987-03-24 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Process for conditioning contaminated waste through cementing
RU2132095C1 (ru) * 1997-12-03 1999-06-20 Московское государственное предприятие Объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды Устройство для цементирования жидких радиоактивных отходов

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
1985, pages 132 - 136 *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2854694C1 (ru) * 2025-08-12 2026-01-15 Акционерное общество "Научно-исследовательский и конструкторский институт монтажной технологии - Атомстрой" (АО "НИКИМТ-Атомстрой") Способ переработки жидких радиоактивных отходов
RU2858046C1 (ru) * 2025-10-29 2026-03-11 Акционерное общество "Научно-исследовательский и конструкторский институт монтажной технологии - Атомстрой" (АО "НИКИМТ-Атомстрой") Способ переработки радиоактивных растворов после дезактивации оборудования реакторов бн
RU2858662C1 (ru) * 2025-10-29 2026-03-23 Акционерное общество "Научно-исследовательский и конструкторский институт монтажной технологии - Атомстрой" (АО "НИКИМТ-Атомстрой") Способ переработки радиоактивных растворов дезактивации оборудования

Also Published As

Publication number Publication date
RU2617113C1 (ru) 2017-04-21
EA201800446A1 (ru) 2019-01-31

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