EP0204634A1 - Verfahren und Einrichtung zum Behandeln von nichtorganischen festen Tritium enthaltenden Abfällen - Google Patents

Verfahren und Einrichtung zum Behandeln von nichtorganischen festen Tritium enthaltenden Abfällen Download PDF

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Publication number
EP0204634A1
EP0204634A1 EP86401184A EP86401184A EP0204634A1 EP 0204634 A1 EP0204634 A1 EP 0204634A1 EP 86401184 A EP86401184 A EP 86401184A EP 86401184 A EP86401184 A EP 86401184A EP 0204634 A1 EP0204634 A1 EP 0204634A1
Authority
EP
European Patent Office
Prior art keywords
waste
gases
detritiation
hydrogen
tank
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.)
Granted
Application number
EP86401184A
Other languages
English (en)
French (fr)
Other versions
EP0204634B1 (de
Inventor
Pierre Giroux
Michel Maj
Gilbert Theis
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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Publication of EP0204634A1 publication Critical patent/EP0204634A1/de
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Publication of EP0204634B1 publication Critical patent/EP0204634B1/de
Anticipated expiration legal-status Critical
Expired - Lifetime 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
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G21F9/308—Processing by melting the waste
    • 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
    • G21F9/02—Treating gases

Definitions

  • the subject of the present invention is a method and a device for the treatment of non-organic solid waste having been in contact with tritium or having contained tritiated products.
  • the present invention specifically relates to a process for treating tritiated waste which is simple and easy to implement and which makes it possible to considerably reduce the tritium content of the treated parts. It also makes it possible to homogenize the residual content, which facilitates the measurement of this content.
  • Gas extraction can be done in several ways.
  • Another method consists in injecting hydrogen into the mass of molten waste, while constantly extracting the atmosphere contained in the enclosure.
  • hydroxide designates all the isotopes of this element, that is to say hydrogen as well as deuterium or tritium.
  • the oxidation of these elements therefore makes it possible to obtain either water, or heavy water, or tritiated water, or a mixture of the different molecular species.
  • the role of the molecular sieve is to retain the water molecules formed during contact with the oxidation catalyst, which makes it possible to trap, among other things, tritiated water. This is then subjected to further processing.
  • the airlock is in the form of a bell that can pivot relative to the tank.
  • the device may also include means for bubbling hydrogen through the mass of molten waste.
  • the means for evacuating the furnace and bringing the gases released during the melting to the detritiation unit comprise at least one pumping group connected to the tank of the furnace by a first pipe and to the detritiation assembly by a second pipe.
  • This pumping group can be a combination of primary pumps and / or secondary pumps. It must be particularly tight vis-à-vis the outside and contain the minimum of organic materials, in particular the minimum of lubricating oil or grease in the parts in contact with the fluid. This relates more particularly to gaseous tritium, tritiated water vapor and possibly tritiated hydrocarbons.
  • the device which is the subject of the invention firstly comprises an oven, bearing the general reference 2, placed inside a glove box 4.
  • This oven is essentially constituted a tank 6 arranged horizontally and open at its upper part.
  • this tank is made of double-walled stainless steel and is cooled by a circulation of water.
  • a crucible 12 of refractory material which contains the tritiated waste 14. These are heated by induction thanks to - a coil 16 when their nature allows. If it is aluminum waste, a graphite crucible can be used to achieve electromagnetic coupling. In this case, the temperature of the liquid mass is of the order of 900 ° C.
  • the liquid mass is at a temperature of the order of 1600 ° C.
  • graphite can be added to the waste in order to facilitate the realization of the electromagnetic coupling.
  • carbon can combine with iron to give a carbide whose melting point is lower than that of stainless steel.
  • the tank 6 is closed by a vacuum valve 18, which is surmounted by an airlock 20 used for the introduction of the products to be treated.
  • the airlock 20 is in the form of a bell open downwards and able to pivot around an axis 22.
  • the airlock is thus movable between an open position 20a shown in dashed lines in the figure and a closed position 20b shown in solid lines.
  • a nacelle 13 containing the waste is introduced inside the airlock from below, when the latter is in the open position, thanks to a cable 24.
  • an ingot mold '15 in which the liquid contained in the crucible 12 is poured once the latter is filled. This facilitates the release of the ingot once solidified.
  • the mold is filled by pivoting the crucible 12.
  • a pipe 26 equipped with a valve 28 places the tank 6 of the oven in communication with a pumping assembly 30 which, in the example shown here, comprises a primary pump 32 and a secondary pump 34.
  • a pumping assembly 30 which, in the example shown here, comprises a primary pump 32 and a secondary pump 34.
  • These pumps allow on the one hand to create a vacuum inside the furnace and, on the other hand, to send the gases released during the melting of the waste 14 to the detritiation unit 36 which will be described later in the remainder of this text.
  • the primary pump 32 or the secondary pump 34 is used, depending on whether one wishes to obtain a more or less high vacuum. It is also possible to sweep the tank 6 with an appropriate gas, for example argon, hydrogen, dry air or helium.
  • a compressed gas bottle 17 placed outside the glove box 4 and connected to the tank 6 by a pipe 19 while the pumping group 30 remains on the way in order to constantly extract the gases contained in the enclosure 6.
  • it can be maintained under a reduced pressure of the order of 300 millibars, or under a primary vacuum, the pressure being less than 1 millibar.
  • it is also possible, while carrying out such a sweep, to inject hydrogen into the mass of molten waste 14, for example by means of a hydrogen bottle 21 placed outside the glove box 4 and connected to the crucible 12 by a pipe 23.
  • An isotope dilution is thus carried out: the content of isotopes of hydrogen isotopes remaining constant, if hydrogen is introduced by bubbling, the hydrogen content is increased and the tritium content is reduced .
  • This method therefore has the effect of accelerating detritiation, especially since the excess hydrogen entrains the tritium which is thus released.
  • the pumping assembly 30 is connected to the detritiation assembly 36 by a pipe 38 fitted with a valve 40.
  • the pipe 38 opens into a container 42, which contains an oxidation catalyst 46 This may be, for example, a product from the Deoxo series marketed by the ENGEL-HARD Company.
  • a pipe 48 connects the container 42 to two containers 50 placed in parallel and each containing a molecular sieve 52.
  • the gases having passed through the detritiation assembly 36 and exiting at the bottom of the containers 50 are extracted through a pipe 54 connected to an extraction device.
  • a regeneration device 53 comprises a cold trap and a circulation pump. It allows a counter-current circulation of dry air in the molecular sieves. This is how the dry air goes from the regenerator 53 to the bottom of the containers 50, passes through the molecular sieves 52 from bottom to top and returns to the regenerator 53 by a pipe 57.
  • the line 48 is equipped with a heat exchanger 49 in order to cool the gases leaving the container 42 containing the oxidation catalyst 46.
  • the airlock is then emptied by means of the pumping group.
  • the vacuum valve is withdrawn and the airlock is in direct communication with the tank 6.
  • the basket 13 is then lowered inside the crucible 12.
  • the main advantage of the airlock is that it allows the successive introduction of several charges without stopping the heating means and without breaking the vacuum.
  • the waste to be treated when placed in bulk, occupies a significant volume since it is essentially containers, pipes, taps, valves, etc. When they are melted, the mass in fusion (and therefore the solid mass that will result after solidification) is much more compact and occupies only part of the volume of the crucible. This is why it is possible to carry out several loads during the same operation in order to completely fill the crucible 12.
  • the tank 6 of the oven is closed in leaktight manner by the valve at vacuum 18 and the vacuum still prevails inside the tank.
  • the nacelle itself melts with the waste and that it is therefore preferable to make it from a light and inexpensive material whose melting point is compatible with that of the waste to be treated.
  • the gases contained in the enclosure 6 are permanently extracted, the gases contained in the products 14 are continuously released during the melting and are evacuated by means of the pumping group 30.
  • tritium is a gas and the Tritiated water vaporizes, this has the effect of removing most of the tritium or tritiated water absorbed in the waste.
  • the gases are sent, through the pipe 38, to the container 42. During their passage through this container, they are in contact with the oxidation catalyst 46, which has the effect of oxidizing the isotopes of hydrogen and in particular to transform tritium into tritiated water.
  • This tritiated water which is in the form of vapor, then passes along the pipe 48 and passes through the containers 50 which contain the molecular sieves 52. During the passage of the gases through these molecular sieves, these retain all the vapor of water, and therefore tritiated water which will then undergo a special treatment.
  • the method and the device which are the subject of the invention have particularly advantageous advantages, the main one of which is that they make it possible to obtain a metallic mass in which the level of tritium (and therefore the activity) has been considerably reduced. This is primarily due to the fact that most of the tritium was removed with the gases during the melting. On the other hand, the waste which initially occupied a large volume and had a large contact surface with air, is found, after fusion and solidification, in the form of a compact mass of small volume and having a contact surface. with little importance. As the degassing rate of the tritiated compounds is proportional to the surface, this rate is considerably reduced by the transformation of a mass of waste into a compact and homogeneous mass. In addition, while in the pipes, valves, containers from the dismantling of the factory, the contamination is extremely variable, the latter is homogeneous in the solid mass obtained after the fusion. We can therefore know the contamination rate by making a single measurement.

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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)
  • Catalysts (AREA)
EP19860401184 1985-06-07 1986-06-03 Verfahren und Einrichtung zum Behandeln von nichtorganischen festen Tritium enthaltenden Abfällen Expired - Lifetime EP0204634B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8508666A FR2583208B1 (fr) 1985-06-07 1985-06-07 Procede et dispositif pour le traitement de dechets trities solides non organiques
FR8508666 1985-06-07

Publications (2)

Publication Number Publication Date
EP0204634A1 true EP0204634A1 (de) 1986-12-10
EP0204634B1 EP0204634B1 (de) 1990-05-23

Family

ID=9320007

Family Applications (1)

Application Number Title Priority Date Filing Date
EP19860401184 Expired - Lifetime EP0204634B1 (de) 1985-06-07 1986-06-03 Verfahren und Einrichtung zum Behandeln von nichtorganischen festen Tritium enthaltenden Abfällen

Country Status (5)

Country Link
EP (1) EP0204634B1 (de)
JP (1) JPS61284697A (de)
DE (1) DE3671563D1 (de)
ES (1) ES8801473A1 (de)
FR (1) FR2583208B1 (de)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2620262A1 (fr) * 1987-09-09 1989-03-10 Commissariat Energie Atomique Procede et installation de traitement de dechets organiques solides contamines par du tritium
DE3930420C1 (en) * 1989-09-12 1990-11-22 Bundesrepublik Deutschland, Vertreten Durch Den Bundesminister Der Verteidigung, Dieser Vertreten Durch Den Praesidenten Des Bundesamtes Fuer Wehrtechnik Und Beschaffung, 5400 Koblenz, De Radioactive waste tritium sepn. - by flushing in gas flow with oxygen, heating and passing tritium through water
DE4029222C1 (en) * 1990-09-14 1991-08-22 Bundesrepublik Deutschland, Vertreten Durch Den Bundesminister Der Verteidigung, Dieser Vertreten Durch Den Praesidenten Des Bundesamtes Fuer Wehrtechnik Und Beschaffung, 5400 Koblenz, De Economical and efficient tritium sepn. - involves passing gas to molten electrodes to ionise molecules, wash tower for absorption and condensate prodn.
EP0503557A1 (de) * 1991-03-13 1992-09-16 Europäische Atomgemeinschaft (Euratom) Verfahren zum Aufarbeiten von Absorberstäben aus wassergekühlten Kernreaktoren
FR2974444A1 (fr) * 2011-04-21 2012-10-26 Commissariat Energie Atomique Dispositif et procede de detritiation
WO2021064304A1 (fr) 2019-10-03 2021-04-08 Onet Technologies Cn Procédé pour décontaminer une pièce métallique contenant un gaz par irradiation laser dans un milieu liquide

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
IT1400531B1 (it) * 2010-06-22 2013-06-11 Commissariat Energie Atomique Processo per la detriziazione di soft housekeeping waste e impianto relativo

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1096072A (en) * 1964-02-27 1967-12-20 Atomic Energy Authority Uk Improvements in or relating to incinerators
DE2434876A1 (de) * 1973-08-27 1975-04-03 Engelhard Min & Chem Verfahren und vorrichtung zum entfernen von tritium und tritiumverbindungen aus gasstroemen
US4285891A (en) * 1979-12-31 1981-08-25 Exxon Nuclear, Inc. Method of removing fission gases from irradiated fuel
EP0036961A2 (de) * 1980-03-26 1981-10-07 Forschungszentrum Jülich Gmbh Behälter zur Lagerung von Tritium

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1096072A (en) * 1964-02-27 1967-12-20 Atomic Energy Authority Uk Improvements in or relating to incinerators
DE2434876A1 (de) * 1973-08-27 1975-04-03 Engelhard Min & Chem Verfahren und vorrichtung zum entfernen von tritium und tritiumverbindungen aus gasstroemen
US4285891A (en) * 1979-12-31 1981-08-25 Exxon Nuclear, Inc. Method of removing fission gases from irradiated fuel
EP0036961A2 (de) * 1980-03-26 1981-10-07 Forschungszentrum Jülich Gmbh Behälter zur Lagerung von Tritium

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2620262A1 (fr) * 1987-09-09 1989-03-10 Commissariat Energie Atomique Procede et installation de traitement de dechets organiques solides contamines par du tritium
EP0307306A1 (de) * 1987-09-09 1989-03-15 Commissariat A L'energie Atomique Verfahren und Vorrichtung zur Behandlung von mit Tritium kontaminierten festen organischen Abfällen
US4882093A (en) * 1987-09-09 1989-11-21 Commissariat A L'energie Atomique Process and installation for the treatment of solid organic waste contaminated by tritium
DE3930420C1 (en) * 1989-09-12 1990-11-22 Bundesrepublik Deutschland, Vertreten Durch Den Bundesminister Der Verteidigung, Dieser Vertreten Durch Den Praesidenten Des Bundesamtes Fuer Wehrtechnik Und Beschaffung, 5400 Koblenz, De Radioactive waste tritium sepn. - by flushing in gas flow with oxygen, heating and passing tritium through water
DE4029222C1 (en) * 1990-09-14 1991-08-22 Bundesrepublik Deutschland, Vertreten Durch Den Bundesminister Der Verteidigung, Dieser Vertreten Durch Den Praesidenten Des Bundesamtes Fuer Wehrtechnik Und Beschaffung, 5400 Koblenz, De Economical and efficient tritium sepn. - involves passing gas to molten electrodes to ionise molecules, wash tower for absorption and condensate prodn.
EP0503557A1 (de) * 1991-03-13 1992-09-16 Europäische Atomgemeinschaft (Euratom) Verfahren zum Aufarbeiten von Absorberstäben aus wassergekühlten Kernreaktoren
WO1992016948A1 (de) * 1991-03-13 1992-10-01 Europäische Atomgemeinschaft (Euratom) Verfahren zum aufarbeiten von absorberstäben aus wassergekühlten kernreaktoren
FR2974444A1 (fr) * 2011-04-21 2012-10-26 Commissariat Energie Atomique Dispositif et procede de detritiation
WO2012146861A3 (fr) * 2011-04-21 2012-12-20 Commissariat A L'energie Atomique Et Aux Energies Alternatives Dispositif et procédé de détritiation
RU2567020C2 (ru) * 2011-04-21 2015-10-27 Коммиссариа А Л'Энержи Атомик Э Оз Энержи Альтернатив Устройство и способ детритирования
WO2021064304A1 (fr) 2019-10-03 2021-04-08 Onet Technologies Cn Procédé pour décontaminer une pièce métallique contenant un gaz par irradiation laser dans un milieu liquide
FR3101558A1 (fr) 2019-10-03 2021-04-09 Onet Technologies Cn Procédé pour décontaminer une pièce métallique contenant un gaz par irradiation laser dans un milieu liquide

Also Published As

Publication number Publication date
ES555832A0 (es) 1987-12-16
ES8801473A1 (es) 1987-12-16
FR2583208A1 (fr) 1986-12-12
JPS61284697A (ja) 1986-12-15
FR2583208B1 (fr) 1992-04-24
EP0204634B1 (de) 1990-05-23
DE3671563D1 (de) 1990-06-28

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