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FR2431755A1 - Procede d'elimination de dechets a partir de solutions de produits de fission et installation appropriee a cet effet - Google Patents

Procede d'elimination de dechets a partir de solutions de produits de fission et installation appropriee a cet effet

Info

Publication number
FR2431755A1
FR2431755A1 FR7916878A FR7916878A FR2431755A1 FR 2431755 A1 FR2431755 A1 FR 2431755A1 FR 7916878 A FR7916878 A FR 7916878A FR 7916878 A FR7916878 A FR 7916878A FR 2431755 A1 FR2431755 A1 FR 2431755A1
Authority
FR
France
Prior art keywords
solutions
waste
disposal
apparatus therefor
fission product
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
FR7916878A
Other languages
English (en)
Other versions
FR2431755B1 (fr
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.)
Forschungszentrum Juelich GmbH
Original Assignee
Kernforschungsanlage Juelich GmbH
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 Kernforschungsanlage Juelich GmbH filed Critical Kernforschungsanlage Juelich GmbH
Publication of FR2431755A1 publication Critical patent/FR2431755A1/fr
Application granted granted Critical
Publication of FR2431755B1 publication Critical patent/FR2431755B1/fr
Expired legal-status Critical Current

Links

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
    • G21F9/301—Processing by fixation in stable solid media
    • G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
    • G21F9/305—Glass or glass like matrix
    • 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
    • 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
    • Y10S159/00—Concentrating evaporators
    • Y10S159/12—Radioactive

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Glass Compositions (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Processing Of Solid Wastes (AREA)
  • Compositions Of Oxide Ceramics (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

L'invention concerne un procédé d'élimintation de déchets à partir de solutions de produits de fission, de même qu'une installation appropriée à cet effet. On concentre les solutions sous vide et sous une pression maximale d'environ 50 torrs pour les amener à une teneur en solides d'au moins environ 15 à 20 %. L'installation comprend un évaporateur sous vide 1 suivi d'un dispositif de mélange 4 avec des points de chargement 5, 6 d'agents décomposant les nitrates et d'agents formateurs de verre, de même qu'un four de vitrification 8 et éventuellement un dispositif de séchage 7. L'invention est utilisée pour simplifier et rendre moins toxique le traitement des solutions de produits de fission.
FR7916878A 1978-07-17 1979-06-29 Procede d'elimination de dechets a partir de solutions de produits de fission et installation appropriee a cet effet Expired FR2431755B1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2831316A DE2831316C2 (de) 1978-07-17 1978-07-17 Abfallbeseitigungsverfahren für rutheniumhaltige salpetersaure Spaltproduktlösungen

Publications (2)

Publication Number Publication Date
FR2431755A1 true FR2431755A1 (fr) 1980-02-15
FR2431755B1 FR2431755B1 (fr) 1986-05-09

Family

ID=6044572

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7916878A Expired FR2431755B1 (fr) 1978-07-17 1979-06-29 Procede d'elimination de dechets a partir de solutions de produits de fission et installation appropriee a cet effet

Country Status (5)

Country Link
US (1) US4344872A (fr)
JP (1) JPS5516300A (fr)
DE (1) DE2831316C2 (fr)
FR (1) FR2431755B1 (fr)
GB (1) GB2025686B (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2607644C2 (ru) * 2015-06-23 2017-01-10 Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") Способ извлечения металлов платиновой группы из продукта кислотного растворения волоксидированного отработавшего ядерного топлива

Families Citing this family (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3200331A1 (de) * 1982-01-08 1983-07-28 GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen "verfahren und anlage zur behandlung von feuchten oder nassen radioaktiven abfallstoffen"
JPS5988692A (ja) * 1982-11-15 1984-05-22 動力炉・核燃料開発事業団 硝酸蒸発処理におけるルテニウムの除染効率改良法
JPS6036999A (ja) * 1983-08-09 1985-02-26 株式会社荏原製作所 放射性ほう酸ナトリウム廃液の減容固化物、減容固化方法及びその装置
EP0246379A3 (fr) * 1985-10-04 1988-10-26 Somafer S.A. Traitement de liquide radioactif
JP2610453B2 (ja) * 1987-10-29 1997-05-14 株式会社日立製作所 硝酸廃液の濃縮方法
JPH0721556B2 (ja) * 1988-03-28 1995-03-08 動力炉・核燃料料開発事業団 気体状ルテニウムの生成を抑制した放射性廃液のガラス溶融固化処理方法
DE3815082A1 (de) * 1988-05-04 1989-11-16 Wiederaufarbeitung Von Kernbre Verfahren und vorrichtung zum behandeln und zum foerdern von feedklaerschlamm zu einer verglasungseinrichtung
US5118447A (en) * 1991-04-12 1992-06-02 Battelle Memorial Institute Thermochemical nitrate destruction
FR2681139B1 (fr) * 1991-09-10 1993-11-05 Matieres Nucleaires Cie Gle Installation pour effectuer plusieurs reactions chimiques successives dans un meme recipient.
DE10009956B4 (de) * 2000-03-02 2004-02-05 W.C. Heraeus Gmbh & Co. Kg Verfahren zur Zerstörung von Nitrat in sauren, wässrigen Lösungen, insbesondere Edelmetall-Lösungen
US6620092B2 (en) * 2001-05-11 2003-09-16 Chem Pro Process and apparatus for vitrification of hazardous waste materials
US7361801B1 (en) 2003-08-27 2008-04-22 352 East Irvin Avenue Limited Partnership Methods for immobilization of nitrate and nitrite in aqueous waste
KR101144420B1 (ko) * 2004-03-18 2012-05-11 가부시끼가이샤 다이셀 고순도 지환식 에폭시 화합물, 그 제조 방법, 경화성에폭시 수지 조성물, 그 경화물, 및 용도
FR2906927B1 (fr) * 2006-10-05 2014-07-25 Commissariat Energie Atomique Procede de vitrification de produits de fission.

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2977194A (en) * 1958-12-03 1961-03-28 John W Loeding Method of reducing aqueous radioactive nuclear wastes to solid form
DE1228009B (de) * 1961-02-09 1966-11-03 Atomkraftwerk Rheinsberg Mit B Verfahren zum Beseitigen von radioaktiven Verunreinigungen aus Fluessigkeiten
GB1129342A (en) * 1965-08-20 1968-10-02 Atomic Energy Authority Uk Improvements in the storage of radioactive liquid effluent
US3962114A (en) * 1975-04-11 1976-06-08 The United States Of America As Represented By The United States Energy Research And Development Administration Method for solidifying liquid radioactive wastes

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1307309A (fr) 1961-09-12 1962-10-26 Commissariat Energie Atomique Traitement des solutions résiduaires de combustibles nucléaires irradiés du type uranium-molybdène
US3120493A (en) * 1962-04-27 1964-02-04 Walter E Clark Suppression of ruthenium volatilization in evaporation and calcination of radioactive waste solutions
JPS4963653A (fr) * 1972-10-23 1974-06-20
DE2609299C2 (de) * 1976-03-06 1983-12-22 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Vorrichtung zur Verfestigung von wäßrigen, radioaktiven Abfall-Lösungen in einem glas- oder keramikartigen Block
DE2632910C2 (de) * 1976-07-21 1982-12-02 Wiegand Karlsruhe Gmbh, 7505 Ettlingen Verfahren zum Eindampfen von Flüssigkeiten, insbesondere von radioaktiven Abwässern
DE2755299A1 (de) * 1976-12-20 1978-06-22 Asea Ab Zylinderfoermiger langgestreckter ofen zur behandlung von material unter hoher temperatur und hohem druck

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2977194A (en) * 1958-12-03 1961-03-28 John W Loeding Method of reducing aqueous radioactive nuclear wastes to solid form
DE1228009B (de) * 1961-02-09 1966-11-03 Atomkraftwerk Rheinsberg Mit B Verfahren zum Beseitigen von radioaktiven Verunreinigungen aus Fluessigkeiten
GB1129342A (en) * 1965-08-20 1968-10-02 Atomic Energy Authority Uk Improvements in the storage of radioactive liquid effluent
US3962114A (en) * 1975-04-11 1976-06-08 The United States Of America As Represented By The United States Energy Research And Development Administration Method for solidifying liquid radioactive wastes

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2607644C2 (ru) * 2015-06-23 2017-01-10 Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") Способ извлечения металлов платиновой группы из продукта кислотного растворения волоксидированного отработавшего ядерного топлива

Also Published As

Publication number Publication date
DE2831316A1 (de) 1980-01-31
GB2025686A (en) 1980-01-23
DE2831316C2 (de) 1984-12-20
GB2025686B (en) 1983-01-19
JPS5516300A (en) 1980-02-04
US4344872A (en) 1982-08-17
FR2431755B1 (fr) 1986-05-09

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ST Notification of lapse