EP0454513B1 - Procédé et four de traitement de déchets incinérables - Google Patents

Procédé et four de traitement de déchets incinérables Download PDF

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Publication number
EP0454513B1
EP0454513B1 EP91400767A EP91400767A EP0454513B1 EP 0454513 B1 EP0454513 B1 EP 0454513B1 EP 91400767 A EP91400767 A EP 91400767A EP 91400767 A EP91400767 A EP 91400767A EP 0454513 B1 EP0454513 B1 EP 0454513B1
Authority
EP
European Patent Office
Prior art keywords
waste
bath
crucible
process according
combustion chamber
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 - Lifetime
Application number
EP91400767A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0454513A3 (fr
EP0454513A2 (fr
Inventor
René Marius Dominique Tanari
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.)
Areva NP SAS
Original Assignee
Framatome SA
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Filing date
Publication date
Application filed by Framatome SA filed Critical Framatome SA
Publication of EP0454513A2 publication Critical patent/EP0454513A2/fr
Publication of EP0454513A3 publication Critical patent/EP0454513A3/fr
Application granted granted Critical
Publication of EP0454513B1 publication Critical patent/EP0454513B1/fr
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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/32Processing by incineration
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F23COMBUSTION APPARATUS; COMBUSTION PROCESSES
    • F23GCREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
    • F23G5/00Incineration of waste; Incinerator constructions; Details, accessories or control therefor
    • F23G5/02Incineration of waste; Incinerator constructions; Details, accessories or control therefor with pretreatment
    • F23G5/033Incineration of waste; Incinerator constructions; Details, accessories or control therefor with pretreatment comminuting or crushing
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F23COMBUSTION APPARATUS; COMBUSTION PROCESSES
    • F23GCREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
    • F23G2204/00Supplementary heating arrangements
    • F23G2204/20Supplementary heating arrangements using electric energy
    • F23G2204/203Microwave
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F23COMBUSTION APPARATUS; COMBUSTION PROCESSES
    • F23GCREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
    • F23G2209/00Specific waste
    • F23G2209/18Radioactive materials

Definitions

  • the present invention relates to methods and furnaces for the treatment of incinerable waste, in particular of low nuclear activity.
  • This notably involves treating technological waste produced during maintenance and repair operations in the active parts of a nuclear installation, such as gloves, coats, overboots, plastics, such as polyethylene containing organic residues, but also operational waste such as resins, organic sludge, oils or emulsions.
  • This waste consists of organic substances carrying radionuclides.
  • GB-A-2 157 062 a process for the treatment of waste containing radionuclides is described, which consists in loading vitreous material in a microwave oven and in melting it therein under an air atmosphere between 1100 and 1500 ° C. Then the oven is placed under an inert gas atmosphere, while modifying the microwave heating and there introduces the waste to be treated to dry and distill it. The oven is then placed in an air atmosphere to burn the waste by modifying the microwave heating. The air and heating flow is then further modified to melt the residue in the vitreous material. In FR-A-2454677, it is proposed to grind solid radioactive waste in order to better attack it with sulfuric acid.
  • the invention relates to a process making it possible to reduce the volumes of waste to be conditioned and to condition this waste, after gasification and / or fusion, without the production of powdery ash or unburnt matter, therefore under very satisfactory safety conditions, with a speed high, while requiring only a reduced investment and the operation of which is very simple, without in particular requiring repeated adjustments of the heating and the atmosphere of an oven, or very high temperatures.
  • the process according to the invention consists in grinding the waste to a particle size of less than 2 mm, in entraining it by a carrier gas in the lower part of a bath based on molten silica, in running only part of the bath in which there are mineral materials, including in particular solid radionuclides in the case of nuclear waste, in a container and allowing the bath to solidify in the container, the entrainment pressure of the carrier gas being just greater than the pressure corresponding to the height of the column formed by the molten bath.
  • cryogenic grinding is carried out at a temperature ranging from -120 to -80 ° C.
  • the prior grinding facilitates not a chemical attack by an acid, but the subsequent operation of pyrolysis of the organic substances of the waste and the subsequent physical operation of melting the mineral matter of the waste in the bath. It contributes, in combination with the height of the bath, to the possibility of treating waste at once, without having to modify the atmosphere above in the bath to carry out separate successive stages of distillation and combustion.
  • Driving by a carrier gas also contributes to this, by ensuring a uniform distribution of the waste in the bath.
  • the ashes and nuclear solid mineral matter thus remain in the bath which is enriched with solid radionuclides and which, once stored after solidification in the container, occupies a much smaller volume than the initial waste.
  • the degradation of organic chains by pyrolysis gives products with simpler molecules, which facilitates complete gasification in a preferably oxidizing atmosphere above the bath, the combustion gases being then sent and purified downstream.
  • the pyrolysis and gasification of the pyrolysis products are independent of the lower calorific values of the treated waste, which makes it possible not to practice prior sorting.
  • the volume of organic carrier waste is transformed into a volume of gas which can be rejected after purification, the residual solid materials being incorporated into the bath, increasing its volume only in small proportions. The reduction in volume is very important and no powdery ash is formed.
  • the complete gasification of the pyrolysis products with simpler molecules eliminates the presence of unburnt matter in the fumes.
  • the carrier gas drive pressure to be just greater than the pressure corresponding to the height of the column formed by the molten bath.
  • a temperature bath is constantly maintained at the bottom of the crucible, which allows continuous treatment, without interrupting the energy balance.
  • the bath has a height of 5 to 40 cm above the level d waste, for a bath temperature of 1000 to 1100 ° C. It is better, in the same way, that the mass of the bath represents from 0.2 to 6 times the hourly mass flow rate of the waste.
  • mineral products can be added to the waste in an amount and of a nature such that the mineral composition of the waste becomes substantially identical to that of the bath. This generally consists of 40 to 100% by weight of SiO2 and from 0 to 60% by weight of other metal oxides, such as alkali metal oxides and boron oxides serving as fluxes.
  • a flux may also be added to the waste, making it possible to melt the mineral materials contained in the waste at a lower temperature and so that the composition of the mineral materials in the waste becomes identical to that of the bath.
  • an oxygen-containing gas is introduced above the bath to effect the gasification of the pyrolysis products in an oxidizing atmosphere above the bath.
  • the simplest carrier gas to use is air, but the carrier gas for introducing waste into the bath can also be a neutral, dry or highly hygrometric or reducing gas or which gives hypostoichiometric oxidation conditions in the bath. . However, it is not necessary to modify the atmosphere above the bath during the process.
  • the invention also relates to a waste treatment oven comprising a crucible provided with a heating device, a waste supply pipe opening out at the bottom of the crucible, a pipe for drawing off a bath opening out into the crucible at a level higher than that of the mouth of the waste supply duct, the top of the crucible communicating with a combustion chamber, which communicates, by a baffled passage upwards, delimited in a vault, with an evacuation chamber, an oxygen-containing gas supply duct opening into the combustion chamber.
  • This oven makes it possible to carry out the treatment, according to the invention, of contaminated waste, the baffled passage allowing the pyrolysis gas to remain long enough in the combustion chamber to be burnt completely there by preventing these gases from going directly into the rest of downstream facility.
  • the installation includes a cryogenic grinding unit, composed of a shredder crusher 1 and a granulator 2, which operate at -120 ° C.
  • the ground waste is sent, via a conduit 3, to a first metering device 4.
  • a second metering device 5 is supplied by a conduit 6 coming from an additive source.
  • the two metering units 4 and 5 open into a duct 7 which is supplied on one side by an air source and which leads to a mixing cyclone 8. From this leaves a rod 9 which passes through the side wall of an oven and opens near the bottom 10 thereof.
  • the refractory material oven has two separate parts.
  • a crucible 11 made of refractory steel at the bottom, containing a molten silicon bath and provided with heating means 12, and an upper part, 13, made of refractory material.
  • a casting rod 14 passes through the bottom 10 and opens into the crucible at a height of 400 mm.
  • the upper part 13 comprises a refractory vault 15 provided with baffled passages 16 which subdivide this upper part into a combustion chamber 17 formed above the siliceous bath and below the vault 15 and into an evacuation chamber 18, at above the arch 15.
  • the upper part 13 is provided with a heating device 19.
  • In the chamber 17 opens an air ramp 20.
  • a duct 21 leads to an air cooler 22 supplied in the air by a line 23 and communicating through a line 24 with a chemical neutralizer 25 which converts chlorine into soluble chloride and which operates in a closed circuit, a pump 26 circulating, through a line 27, a solution of alkali metal carbonate or sodium hydroxide in the neutralizer 25.
  • a conduit 28 leads therefrom to a very high efficiency filter 29. The efficiency of the filter is 99.98%. This filter is intended to remove radioactive aerosols. From the filter 29, a duct 30 leads to a fan 31 and to a chimney 32.
  • the doser 4 sends 667 g of waste / minute in the duct 7.
  • the doser 5 sends 19 g of sodium carbonate / minute into line 7.
  • the air flow rate in duct 7 is 3 m3 normal / hour under pressure.
  • the crucible 11 made of refractory steel has a diameter of 500 mm and a height of 1000 mm, which corresponds to a capacity of 196 liters. It contains a molten silicon bath composed for 61% by weight of SiO2 and for 39% by weight of a mixture of B2O3 and Na2O. The melting point is 900 ⁇ 20 ° C. The operating temperature is 1000 ⁇ 50 ° C. The height of the bath, at the start of the treatment, is 400 mm (78 liters corresponding substantially to 195 kg). This mass constitutes the permanent liquid base of the crucible which is at a temperature of 1000 ° C.
  • the orifice of the waste injection rod 9 is located 100 mm above the bottom 10.
  • the temperature at the outlet of the cooler is approximately 80 ° C.
  • the binders and mineral additives in the waste are retained in the silica bath.
  • the variation in the volume of the bath, for an introduction rate of 40 kg / hour of waste is 0.7 liters / hour and this bath is poured by the cane 14 every 96 hours for a unit treating 40 kg ⁇ 1.
  • the effluents exiting through the stack 32 include 49,000 normal m3 of CO2 / hour, 52 m3 of H2O / hour and 2,600 m3 of air / hour.
  • Environmental pollution is negligible, since the process only generates a 97% air discharge at 20 ° C. Any contaminants are confined in the pouring glass or trapped on the specific filter and the HCl content remains below 100 mg / m3 normal.
  • the metering device 4 supplies 670 g of waste / minute to the duct 7.
  • the metering unit 5 supplies 25 g of sodium carbonate / minute to the duct 7.
  • 5 m3 normal / hour of air are sent to the chamber 17.
  • Via line 23 pass 910 m3 / hour, at a temperature of 20 ° C.
  • the temperature at the outlet of the cooler is around 80 ° C. In this case, the neutralizer 25 is removed from the installation.
  • the chemical composition of the bath is 60% by weight of SiO2 and 40% by weight of the mixture of B2O3 and Na2O. Its melting point is 900 ⁇ 20 ° C. Its operating temperature is 1000 ⁇ 50 ° C.
  • the variation in the volume of the bath essentially produced by the glass bottles for an introduction rate of 40 kg of waste / hour is 12.5 liters / hour and a casting is carried out by the cane 14 every 8 hours (100 liters ).
  • composition of the glass obtained changes little, as a function of time, the composition remaining substantially identical to the initial composition.
  • the gaseous effluents leaving the chimney are 16 m3 normal CO de / hour, 16 m3 H2O / hour and 1000 m3 normal air / hour.
  • the process only generates a discharge at 97% air and at 20 ° C. Any contaminants are confined in the poured glass or trapped on the filter.
  • Waste from the chemical industry is mainly composed of phenyl mercury.
  • the doser 4 supplies 167 g of waste / minute to the pipe 7.
  • the doser 5 sends 22 g of a mixture of alkali metal carbonate and silica / minute to the pipe 7.
  • the chemical neutralizer transforms HgO into soluble salts.
  • the bath contains 60% by weight of SiO2 and 40% by weight of Na2O. Its melting point is 900 ⁇ 20 ° C. Its operating temperature is 1000 ⁇ 50 ° C.
  • the variation in the volume of the bath, for an introduction rate of 10 kg of waste / hour, is 3.2 liters / hour.
  • the gaseous effluents include 11 normal m3 of CO2 / hour, 4 normal m3 of H2O / hour and 700 m3 of air / hour.
  • the process only generates a discharge at 98.5% by weight of air and at 20 ° C (the Hg content is less than 0.3 mg.m3 normal.

Landscapes

  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • Processing Of Solid Wastes (AREA)
  • Gasification And Melting Of Waste (AREA)
  • Incineration Of Waste (AREA)
  • Crucibles And Fluidized-Bed Furnaces (AREA)
  • Processing And Handling Of Plastics And Other Materials For Molding In General (AREA)
EP91400767A 1990-03-23 1991-03-21 Procédé et four de traitement de déchets incinérables Expired - Lifetime EP0454513B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR9003728 1990-03-23
FR9003728A FR2659877B1 (fr) 1990-03-23 1990-03-23 Procede et four de traitement de dechets incinerables.

Publications (3)

Publication Number Publication Date
EP0454513A2 EP0454513A2 (fr) 1991-10-30
EP0454513A3 EP0454513A3 (fr) 1991-12-04
EP0454513B1 true EP0454513B1 (fr) 1995-06-28

Family

ID=9395037

Family Applications (1)

Application Number Title Priority Date Filing Date
EP91400767A Expired - Lifetime EP0454513B1 (fr) 1990-03-23 1991-03-21 Procédé et four de traitement de déchets incinérables

Country Status (12)

Country Link
US (1) US5277846A (es)
EP (1) EP0454513B1 (es)
JP (1) JPH04222682A (es)
AT (1) ATE124563T1 (es)
BR (1) BR9101130A (es)
CZ (1) CZ284662B6 (es)
DE (1) DE69110744T2 (es)
ES (1) ES2075379T3 (es)
FR (1) FR2659877B1 (es)
HU (1) HU210642B (es)
MX (1) MX172258B (es)
SK (1) SK281037B6 (es)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2141076C1 (ru) * 1993-04-06 1999-11-10 Осмелт Лимитед Способ обработки углеродсодержащего материала
US5424042A (en) * 1993-09-13 1995-06-13 Mason; J. Bradley Apparatus and method for processing wastes
US5611766A (en) * 1996-02-06 1997-03-18 Envitco, Inc. Transportable, modular vitrification system for the treatment of waste material
GB9619523D0 (en) * 1996-09-19 1996-10-30 Ferguson Ian G Ferguson cryonator/cryotory
UA57884C2 (uk) * 1999-10-14 2003-07-15 Дейвід БРЕДБЕРІ Спосіб обробки радіоактивного графіту
DE10148146B4 (de) * 2001-09-28 2009-08-27 Forschungszentrum Jülich GmbH Verfahren zur Entsorgung eines mit mindestens einem Radiotoxikum kontaminierten Gegenstandes aus Reaktorgraphit und/oder Kohlestein
KR100450003B1 (ko) * 2002-01-08 2004-09-30 현대모비스 주식회사 고체 방사성폐기물 정량투입장치
JP5877483B2 (ja) * 2012-02-13 2016-03-08 清水建設株式会社 放射性物質を含む可燃性廃棄物の減容化処理方法
CN104751929B (zh) * 2013-12-26 2018-07-06 中国辐射防护研究院 集成化低放可燃固体废物焚烧装置
JP6689012B2 (ja) * 2015-07-27 2020-04-28 瀬倉株式会社 原子力施設の放射線管理区域における洗濯による放射能汚染水の発生を抑止する保護衣等の取扱方法
FR3080707B1 (fr) * 2018-04-25 2020-05-01 Seche Eco Services Procede de traitement de dechets bitumines radioactifs

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2631220C2 (de) * 1976-07-12 1986-03-06 Sorg-GmbH & Co KG, 8770 Lohr Schmelzofen zum Einschmelzen von radioaktiven Stoffen in Glas
DE2916203A1 (de) * 1979-04-21 1980-11-06 K E W A Kernbrennstoff Wiedera Verfahren zur behandlung von brennbaren, festen, radioaktiven abfaellen
DE3247349C1 (de) * 1982-12-22 1984-05-24 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Schmelzofen zur Verglasung von hochradioaktivem Abfall
CA1200826A (en) * 1983-06-17 1986-02-18 Majesty (Her) In Right Of Canada As Represented By Atomic Energy Of Canada Limited/L'energie Atomique Du Canada Limitee Joule melter for the processing of radioactive wastes
JPS60203900A (ja) * 1984-03-29 1985-10-15 日本原子力研究所 放射性核種を含む廃棄物の処理方法
US4632690A (en) * 1985-06-04 1986-12-30 Colwell Jr Robert E Hazardous waste removal method and apparatus
US4735784A (en) * 1986-07-11 1988-04-05 Morrison-Knudsen Company, Inc. Method of treating fluoride contaminated wastes
DE3815082A1 (de) * 1988-05-04 1989-11-16 Wiederaufarbeitung Von Kernbre Verfahren und vorrichtung zum behandeln und zum foerdern von feedklaerschlamm zu einer verglasungseinrichtung
US5067978A (en) * 1989-08-24 1991-11-26 Fowler Benjamin P Method for the removal of lead from waste products
US5022329A (en) * 1989-09-12 1991-06-11 The Babcock & Wilcox Company Cyclone furnace for hazardous waste incineration and ash vitrification
US4977837A (en) * 1990-02-27 1990-12-18 National Recovery Technologies, Inc. Process and apparatus for reducing heavy metal toxicity in fly ash from solid waste incineration
FR2659876B1 (fr) * 1990-03-23 1992-08-21 Tanari Rene Procede et four de traitement de dechets fusibles.

Also Published As

Publication number Publication date
EP0454513A3 (fr) 1991-12-04
SK281037B6 (sk) 2000-11-07
ATE124563T1 (de) 1995-07-15
MX172258B (es) 1993-12-08
BR9101130A (pt) 1991-11-05
CS9100762A2 (en) 1991-11-12
HUT56744A (en) 1991-10-28
FR2659877A1 (fr) 1991-09-27
EP0454513A2 (fr) 1991-10-30
FR2659877B1 (fr) 1992-11-27
CZ284662B6 (cs) 1999-01-13
ES2075379T3 (es) 1995-10-01
DE69110744T2 (de) 1995-11-23
US5277846A (en) 1994-01-11
DE69110744D1 (de) 1995-08-03
JPH04222682A (ja) 1992-08-12
HU210642B (en) 1995-06-28

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