EP0307306B1 - 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

Info

Publication number
EP0307306B1
EP0307306B1 EP88402247A EP88402247A EP0307306B1 EP 0307306 B1 EP0307306 B1 EP 0307306B1 EP 88402247 A EP88402247 A EP 88402247A EP 88402247 A EP88402247 A EP 88402247A EP 0307306 B1 EP0307306 B1 EP 0307306B1
Authority
EP
European Patent Office
Prior art keywords
waste
tritium
steam
temperature
water
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
EP88402247A
Other languages
English (en)
French (fr)
Other versions
EP0307306A1 (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
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of EP0307306A1 publication Critical patent/EP0307306A1/de
Application granted granted Critical
Publication of EP0307306B1 publication Critical patent/EP0307306B1/de
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

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 consists in bringing said waste into contact with water vapor at a temperature T and a pressure P at most equal to the vapor pressure p s of water at temperature T to extract from the water vapor at least part of the tritium present in the waste, and then to condense the water vapor 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 under a pressure below atmospheric pressure in order to have more suitable 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.
  • FR-A- 2 279 205 discloses a treatment enclosure in which a gaseous transport medium can be circulated, possibly containing more water vapor which is then condensed, but this enclosure is intended for 'evaporation of liquid waste while the drying chamber of the invention is intended for the treatment of solid waste contaminated with tritium.
  • 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 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.

Landscapes

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

Claims (8)

  1. Verfahren zur Behandlung organischer, fester, mit Tritium kontaminierter Abfälle, bestehend aus dem Zusammenbringen der Abfälle mit Wasserdampf bei einer Temperatur T und einem Druck P, welcher gleich dem Wasserdampfdruck ps bei der Temperatur T ist, um die Abfälle mit Wasser zu sättigen und das Tritium im Wasserdampf zu verdünnen und darauf dem Kondensieren des Wasserdampfes, um das Tritium aus den Abfällen in Form tritiierten Wassers zu gewinnen.
  2. Verfahren zur Behandlung organischer, fester, mit Tritium kontaminierter Abfälle, bestehend aus dem Zusammenbringen der Abfälle mit trockenem Wasserdampf bei einer Temperatur T und einem Druck P, welcher niedriger als der Wasserdampfdruck ps bei der Temperatur T ist, um die Abfälle zu trocknen und aus ihnen den Hauptteil Tritium, den sie enthalten, zu extrahieren, und darauf dem Kondensieren des Wasserdampfes, um das Tritium aus den kontaminierten Abfällen zu gewinnen.
  3. Verfahren gemäß einem der Ansprüche 1 und 2, dadurch gekennzeichnet, daß die Temperatur T niedriger als die Zersetzungs- oder Schmelztemperatur der behandelten, organischen, festen Abfälle ist.
  4. Verfahren gemäß Anspruch 3, dadurch gekennzeichnet, daß die Temperatur T niedriger als 80°C ist.
  5. Verfahren gemäß Anspruch 2, dadurch gekennzeichnet, daß der Wasserdampfdruck P 13,5 bis 27 kPa (100 bis 200 Torr) beträgt.
  6. Verfahren gemäß einem der Ansprüche 1 bis 5, dadurch gekennzeichnet, daß man unter einem niedrigeren Innendruck als Atmosphärendruck arbeitet.
  7. Vorrichtung zur Behandlung organischer, fester, mit Tritium kontaminierter Abfälle, dadurch gekennzeichnet, daß sie
    a) einen zum Aufnehmen der zu behandelnden festen Abfälle geeigneten Trokenbehälter (1),
    b) Heizmittel (19) des Trockenbehälters,
    c) Mittel (7, 25, 27) zum Umwälzen des Wasserdampfes im Trockenbehälter bei einer Temperatur T und einem Druck P, welcher kleiner gleich dem Wasserdampfdruck ps bei der Temperatur T ist,
    d) Mittel (11, 13) zum Kondensieren des aus dem Trockenbehälter austretenden Wasserdampfes, und
    e) Mittel (15) zum Lagern des auf diese Weise kondensierten Wassers,
    umfaßt.
  8. Vorrichtung gemäß Anspruch 7, dadurch gekennzeichnet, daß die Mittel zum Umwälzen des Wasserdampfes im Trockenbehälter bei einer Temperatur T und einem Druck P einen Dampferzeuger (7) umfassen, dessen Dampfraum mit dem Trockenbehälter durch eine Leitung (25) verbunden ist, welche mit einem Regulierventil versehen ist, wobei die Leitung in den Trockenbehälter unter einem Rost (17) mündet, welcher die zu behandelnden Abfälle trägt.
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 EP0307306A1 (de) 1989-03-15
EP0307306B1 true 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)

Families Citing this family (14)

* 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
GB9005707D0 (en) * 1990-03-14 1990-05-09 Atomic Energy Authority Uk Tritium removal
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
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
RU2226727C1 (ru) * 2002-11-18 2004-04-10 Общество с ограниченной ответственностью "Севергазпром" Устройство для дезактивации твердых радиоактивных веществ
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

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4178350A (en) * 1973-08-27 1979-12-11 Engelhard Minerals & Chemicals Corp. Removal of tritium and tritium-containing compounds from a gaseous stream
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
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
AT338388B (de) * 1975-06-26 1977-08-25 Oesterr Studien Atomenergie Verfahren und vorrichtung zur uberfuhrung von radioaktiven ionenaustauscherharzen in eine lagerfahige form
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
FR2583208B1 (fr) * 1985-06-07 1992-04-24 Commissariat Energie Atomique Procede et dispositif pour le traitement de dechets trities solides non organiques
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

Also Published As

Publication number Publication date
FR2620262B1 (fr) 1989-11-17
CA1333324C (fr) 1994-12-06
JPH0199000A (ja) 1989-04-17
DE3876345T2 (de) 1993-05-27
DE3876345D1 (de) 1993-01-14
US4882093A (en) 1989-11-21
JP2807237B2 (ja) 1998-10-08
EP0307306A1 (de) 1989-03-15
FR2620262A1 (fr) 1989-03-10

Similar Documents

Publication Publication Date Title
CA1333324C (fr) Procede et installation de traitement de dechets organiques solides contamines par du tritium
CA1195594A (fr) Procede et installation de decapage d'objets pourvus d'un revetement
JP2904920B2 (ja) 釣り合いのとれた蒸気流を供給する方法およびそれを実施するための装置
US4108605A (en) Hydrogen purification and storage system
FR2472942A1 (fr) Installation d'evaporation a plusieurs etages a systeme integre de recyclage de chaleur
JPS5915718B2 (ja) 水銀含有スラッジから水銀を除去する方法
US3525673A (en) Closed,controlled system for carbonizing organic refuse
GB2178588A (en) Method and apparatus of treatment of radioactive liquid waste
SU1367853A3 (ru) Способ получени нитрата аммони
JP3843940B2 (ja) ガス化改質方式における廃棄物からの混合塩製造方法
US5740215A (en) System for backcooling radioactive-waste containers
EP0116529B2 (de) Verfahren und Anlage zur Erzeugung von Ammoniumnitrat
JP2008207118A (ja) アンモニア性窒素含有排水の処理方法、処理装置、及び処理システム
JPS54156999A (en) Device for processing radioactive gaseous wastes
FI111086B (fi) Menetelmä ja laite kasvihuonekaasupäästöjen vähentämiseksi
FR2459825A1 (fr) Procede d'extinction d'une matiere en vrac chauffee, notamment du coke
JP2564132B2 (ja) 高速炉炉心構成要素のナトリウム除去処理設備
JP2004340769A (ja) 有機酸除染廃液の処理方法および装置
FR2729676A1 (fr) Procede et dispositif de regeneration d'une solution usagee de decapage d'elements en alliage de zirconium
JP4384378B2 (ja) 有機性廃棄物の乾燥装置および乾燥方法
EP0276876B1 (de) Verfahren zum Dampfentfetten von Gegenständen
FR2677799A1 (fr) Procede pour eliminer des ions d'iode radioactif.
JPH1128724A (ja) 発泡スチロールリサイクルシステム
CH518235A (fr) Procédé et dispositif de purification isotopique de l'eau lourde
JP2932613B2 (ja) 溶融炭酸塩型燃料電池を利用したｃｏ▲下２▼回収装置の運転方法

Legal Events

Date Code Title Description
PUAI Public reference made under article 153(3) epc to a published international application that has entered the european phase

Free format text: ORIGINAL CODE: 0009012

AK Designated contracting states

Kind code of ref document: A1

Designated state(s): BE CH DE GB IT LI SE

17P Request for examination filed

Effective date: 19890819

17Q First examination report despatched

Effective date: 19910418

GRAA (expected) grant

Free format text: ORIGINAL CODE: 0009210

AK Designated contracting states

Kind code of ref document: B1

Designated state(s): BE CH DE GB IT LI SE

REF Corresponds to:

Ref document number: 3876345

Country of ref document: DE

Date of ref document: 19930114

ITF It: translation for a ep patent filed
GBT Gb: translation of ep patent filed (gb section 77(6)(a)/1977)

Effective date: 19930216

PLBE No opposition filed within time limit

Free format text: ORIGINAL CODE: 0009261

STAA Information on the status of an ep patent application or granted ep patent

Free format text: STATUS: NO OPPOSITION FILED WITHIN TIME LIMIT

26N No opposition filed
EAL Se: european patent in force in sweden

Ref document number: 88402247.6

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: SE

Payment date: 19950829

Year of fee payment: 8

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: BE

Payment date: 19950901

Year of fee payment: 8

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: CH

Payment date: 19950913

Year of fee payment: 8

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: SE

Effective date: 19960908

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: LI

Effective date: 19960930

Ref country code: CH

Effective date: 19960930

Ref country code: BE

Effective date: 19960930

BERE Be: lapsed

Owner name: COMMISSARIAT A L'ENERGIE ATOMIQUE ETABLISSEMENT D

Effective date: 19960930

REG Reference to a national code

Ref country code: CH

Ref legal event code: PL

EUG Se: european patent has lapsed

Ref document number: 88402247.6

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: GB

Payment date: 20010905

Year of fee payment: 14

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: DE

Payment date: 20010928

Year of fee payment: 14

REG Reference to a national code

Ref country code: GB

Ref legal event code: IF02

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: GB

Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES

Effective date: 20020907

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: DE

Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES

Effective date: 20030401

GBPC Gb: european patent ceased through non-payment of renewal fee

Effective date: 20020907

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: IT

Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES;WARNING: LAPSES OF ITALIAN PATENTS WITH EFFECTIVE DATE BEFORE 2007 MAY HAVE OCCURRED AT ANY TIME BEFORE 2007. THE CORRECT EFFECTIVE DATE MAY BE DIFFERENT FROM THE ONE RECORDED.

Effective date: 20050907