EP0307306A1 - Verfahren und Vorrichtung zur Behandlung von mit Tritium kontaminierten festen organischen Abfällen - Google Patents

Verfahren und Vorrichtung zur Behandlung von mit Tritium kontaminierten festen organischen Abfällen Download PDF

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Publication number
EP0307306A1
EP0307306A1 EP88402247A EP88402247A EP0307306A1 EP 0307306 A1 EP0307306 A1 EP 0307306A1 EP 88402247 A EP88402247 A EP 88402247A EP 88402247 A EP88402247 A EP 88402247A EP 0307306 A1 EP0307306 A1 EP 0307306A1
Authority
EP
European Patent Office
Prior art keywords
waste
pressure
temperature
water
tritium
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
EP88402247A
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English (en)
French (fr)
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EP0307306B1 (de
Inventor
Pierre Giroux
Jean-Claude Durand
Dominique Ochem
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 EP0307306A1 publication Critical patent/EP0307306A1/de
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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
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S422/00—Chemical apparatus and process disinfecting, deodorizing, preserving, or sterilizing
    • Y10S422/903—Radioactive material apparatus

Definitions

  • the present invention relates to a method for treating solid organic waste contaminated with tritium.
  • the present invention specifically relates to a process for treating solid organic waste contaminated with tritium which makes it easy to achieve this objective.
  • the method according to the invention for treating solid organic waste contaminated with tritium is characterized in that said waste is brought into contact with water vapor under conditions such that it is extracted in the vapor of water at least part of the tritium present in the waste and in that the water vapor is then condensed to recover the tritium from the waste in the form of tritiated water.
  • water vapor is used at a temperature T and a pressure P equal to the vapor pressure p s of the water at the temperature T.
  • dry steam is used at a temperature T and a pressure P lower than the vapor pressure p s of water at temperature T.
  • the tritium present in solid waste is generally in the form of free tritiated water as a result of a spontaneous reaction of tritium with the oxygen in the air, the activation energy of the reaction. being brought by ⁇ radiation tritium.
  • tritium is easily transformed into tritiated water.
  • this free tritiated water is extracted by bringing the waste into contact with steam, which makes it possible to carry out a drying of the waste and to recover the tritium in the form of easy-to-store tritiated water.
  • the waste is brought into contact with the water vapor at a pressure below the atomospheric pressure in order to have more appropriate treatment conditions, at low temperatures.
  • the temperature of the water vapor T must be lower than the degradation, melting or decomposition temperature of the treated solid waste.
  • the installation comprises a drying enclosure 1 for solid waste into which is introduced by a pipe 3 provided with orifices 5 steam coming from a steam generator 7.
  • the steam leaves the drying enclosure via line 9 fitted with a valve 10 and it is condensed in a condenser in two successive stages 11 and 13. It can then be stored in the form of tritiated water in tank 15.
  • the drying chamber 1 is provided with an open grid 17 on which the waste to be treated can be placed.
  • This grid 17 is itself located above the duct 5 provided with the steam outlet orifices 3.
  • the enclosure 1 is heat-insulated and it includes heating means 19 which make it possible to maintain it at the desired temperature, that is to say at the temperature T.
  • the steam generator 7 consists of a heat-insulated enclosure provided at its lower part with heating means 21 to bring the water 23 it contains to temperature T.
  • a pipe 25 connects the steam space of the generator 7 to the pipe 3 for introducing waste into the enclosure 1 and is provided with an adjustment valve 27 making it possible to bring the pressure of the steam to the desired value, that is to say at a value generally lower than the vapor pressure p s of the water 23 contained in the steam generator 7.
  • the two-stage condenser comprises a first stage 11 cooled by water at 15 ° C and a second stage 13 cooled by liquid nitrogen.
  • the waste to be treated is first placed on the perforated grid 17 of the drying enclosure 1, then the pressure throughout the installation is brought to a value below atmospheric pressure using a group of non-vacuum pumps. shown in the drawing.
  • the water from the steam generator 7 is then brought to the desired temperature T and the temperature of the drying chamber 1 is adjusted to the same temperature T.
  • the valve 27 is then opened by adjusting it so as to lower the pressure P of the steam introduced into the drying chamber 1 at a value lower than the vapor pressure p s of the water 23 of the steam generator 7.
  • the valve 10 of the pipe 9 is also opened and the water vapor in the drying chamber 1 for the time required to extract the tritium from the waste.
  • the vapor is condensed successively in the condensers 11 and 13 then stored in tank 15.
  • the waste is introduced into enclosure 1 which has a volume of 2 m3.
  • the water from the steam generator 7 is then brought to a temperature of 60 ° C. and the temperature of the enclosure 1 is also adjusted to 60 ° C.
  • the pressure P of the vapor introduced into the enclosure 1 is 20 kPa (200 mbar).
  • 25 kg of waste containing less than 2 ⁇ Ci / g of tritium are obtained, the activity of the water leaving the condensers is 5 Ci / l.
  • the second mode of implementation of the method of the invention is used, that is to say the steam drying of the waste, to extract waste similar to that of Example 1 for the most part. of the tritium they contain.
  • drying with unsaturated steam is more suitable since there is good heat conduction and good self-diffusion of the tritiated water in the water.

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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)
EP88402247A 1987-09-09 1988-09-07 Verfahren und Vorrichtung zur Behandlung von mit Tritium kontaminierten festen organischen Abfällen Expired - Lifetime EP0307306B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8712510 1987-09-09
FR8712510A FR2620262B1 (fr) 1987-09-09 1987-09-09 Procede et installation de traitement de dechets organiques solides contamines par du tritium

Publications (2)

Publication Number Publication Date
EP0307306A1 true EP0307306A1 (de) 1989-03-15
EP0307306B1 EP0307306B1 (de) 1992-12-02

Family

ID=9354749

Family Applications (1)

Application Number Title Priority Date Filing Date
EP88402247A Expired - Lifetime EP0307306B1 (de) 1987-09-09 1988-09-07 Verfahren und Vorrichtung zur Behandlung von mit Tritium kontaminierten festen organischen Abfällen

Country Status (6)

Country Link
US (1) US4882093A (de)
EP (1) EP0307306B1 (de)
JP (1) JP2807237B2 (de)
CA (1) CA1333324C (de)
DE (1) DE3876345T2 (de)
FR (1) FR2620262B1 (de)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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.
US5707592A (en) * 1991-07-18 1998-01-13 Someus; Edward Method and apparatus for treatment of waste materials including nuclear contaminated materials

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB9005707D0 (en) * 1990-03-14 1990-05-09 Atomic Energy Authority Uk Tritium removal
FR2777090B1 (fr) 1998-04-07 2000-05-05 Commissariat Energie Atomique Procede de msesure de l'activite tritium d'un fut de dechets radioactifs
DE19944776C2 (de) * 1999-09-17 2003-06-18 Karlsruhe Forschzent Verfahren zur Tritiumdekontamination der ersten Wand einer Einrichtung zur Durchführung von Kernfusionen
KR100956694B1 (ko) * 2008-01-15 2010-05-10 세안기술 주식회사 고체 방사성 폐기물 처리장치 및 방법
JP5717348B2 (ja) * 2010-02-02 2015-05-13 国立大学法人富山大学 トリチウム汚染物の除染方法およびその除染システム
IT1401192B1 (it) * 2010-06-16 2013-07-12 Enea Agenzia Naz Per Le Nuove Tecnologie L En E Lo Sviluppo Economico Sostenibile Reattore a membrana per il trattamento di gas contenenti trizio
IT1400531B1 (it) * 2010-06-22 2013-06-11 Commissariat Energie Atomique Processo per la detriziazione di soft housekeeping waste e impianto relativo
US8597471B2 (en) 2010-08-19 2013-12-03 Industrial Idea Partners, Inc. Heat driven concentrator with alternate condensers
CN111524634B (zh) * 2018-12-25 2024-05-14 中国原子能科学研究院 一种含氚放射性固体废物处理系统
CN111613360B (zh) * 2019-03-05 2022-10-28 中国原子能科学研究院 一种含氚放射性固体湿废物的除氚工艺及装置

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2434876A1 (de) * 1973-08-27 1975-04-03 Engelhard Min & Chem Verfahren und vorrichtung zum entfernen von tritium und tritiumverbindungen aus gasstroemen
FR2279205A1 (fr) * 1973-12-27 1976-02-13 Magyar Tudomanyos Akademi Izot Procede et appareil de concentration de dechets radioactifs liquides a des temperatures inferieures a leurs points d'ebullition et en vue de leur stockage final
FR2317740A1 (fr) * 1975-06-26 1977-02-04 Ver Edelstahlwerke Ag Transformation par chauffage de resines echangeurs d'ions radioactives en produits stockables
EP0204634A1 (de) * 1985-06-07 1986-12-10 Commissariat A L'energie Atomique Verfahren und Einrichtung zum Behandeln von nichtorganischen festen Tritium enthaltenden Abfällen

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4470955A (en) * 1973-08-27 1984-09-11 Engelhard Corporation Removal of tritiated species from gas streams comprised thereof
US3937649A (en) * 1973-10-31 1976-02-10 Ridgely John N Process and system for removing tritium
JPS5852199B2 (ja) * 1973-11-02 1983-11-21 株式会社日立製作所 ホウシヤセイトリチウムカイシユウコテイホウ
DE2711368A1 (de) * 1977-03-16 1978-09-21 Hoechst Ag Verfahren zum zurueckhalten von fluechtigen radioaktiven substanzen, die bei der aufarbeitung von kernbrennstoffen anfallen
DE3011602A1 (de) * 1980-03-26 1981-10-08 Kernforschungsanlage Jülich GmbH, 5170 Jülich Verfahren und vorrichtung zur endlagerung von tritium, insbesondere tritiumabfaellen aus kernkraftwerken, mit der moeglichkeit der tritiumrueckgewinnung
DE3025494C2 (de) * 1980-07-04 1986-01-16 Max-Planck-Gesellschaft zur Förderung der Wissenschaften e.V., 3400 Göttingen Verfahren zum Entfernen von Tritium aus einem Gasgemisch
JPS5927878U (ja) * 1982-08-09 1984-02-21 高田　津木男 選別装置
JPS59119297A (ja) * 1982-12-25 1984-07-10 株式会社東芝 放射性気体廃棄物処理装置
US4619809A (en) * 1983-03-30 1986-10-28 The Babcock & Wilcox Company Steam generation and reheat apparatus
JPS6022319U (ja) * 1983-07-21 1985-02-15 同和鉱業株式会社 合成樹脂材溶着器
US4657747A (en) * 1984-10-17 1987-04-14 The United States Of America As Represented By The United States Department Of Energy Recovery of tritium from tritiated molecules
JPH0631834B2 (ja) * 1986-02-14 1994-04-27 株式会社日立製作所 可燃性ガス再結合装置

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2434876A1 (de) * 1973-08-27 1975-04-03 Engelhard Min & Chem Verfahren und vorrichtung zum entfernen von tritium und tritiumverbindungen aus gasstroemen
FR2279205A1 (fr) * 1973-12-27 1976-02-13 Magyar Tudomanyos Akademi Izot Procede et appareil de concentration de dechets radioactifs liquides a des temperatures inferieures a leurs points d'ebullition et en vue de leur stockage final
FR2317740A1 (fr) * 1975-06-26 1977-02-04 Ver Edelstahlwerke Ag Transformation par chauffage de resines echangeurs d'ions radioactives en produits stockables
EP0204634A1 (de) * 1985-06-07 1986-12-10 Commissariat A L'energie Atomique Verfahren und Einrichtung zum Behandeln von nichtorganischen festen Tritium enthaltenden Abfällen

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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.
US5707592A (en) * 1991-07-18 1998-01-13 Someus; Edward Method and apparatus for treatment of waste materials including nuclear contaminated materials

Also Published As

Publication number Publication date
DE3876345D1 (de) 1993-01-14
JPH0199000A (ja) 1989-04-17
FR2620262A1 (fr) 1989-03-10
CA1333324C (fr) 1994-12-06
US4882093A (en) 1989-11-21
DE3876345T2 (de) 1993-05-27
JP2807237B2 (ja) 1998-10-08
FR2620262B1 (fr) 1989-11-17
EP0307306B1 (de) 1992-12-02

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