FR2419907A1 - Procede de recuperation de composes d'uranium a partir d'eaux residuaires de la conversion d'uranylcarbonate d'ammonium - Google Patents

Procede de recuperation de composes d'uranium a partir d'eaux residuaires de la conversion d'uranylcarbonate d'ammonium

Info

Publication number
FR2419907A1
FR2419907A1 FR7905075A FR7905075A FR2419907A1 FR 2419907 A1 FR2419907 A1 FR 2419907A1 FR 7905075 A FR7905075 A FR 7905075A FR 7905075 A FR7905075 A FR 7905075A FR 2419907 A1 FR2419907 A1 FR 2419907A1
Authority
FR
France
Prior art keywords
cpds
degrees
waste water
uranium
simplified process
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.)
Withdrawn
Application number
FR7905075A
Other languages
English (en)
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.)
Reaktor Brennelement Union GmbH
Original Assignee
Reaktor Brennelement Union 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 Reaktor Brennelement Union GmbH filed Critical Reaktor Brennelement Union GmbH
Publication of FR2419907A1 publication Critical patent/FR2419907A1/fr
Withdrawn legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0278Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries by chemical methods
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/01Oxides; Hydroxides
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/01Oxides; Hydroxides
    • C01G43/025Uranium dioxide

Landscapes

  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • General Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Removal Of Specific Substances (AREA)

Abstract

On chauffe à environ 95 degrés C, à travers un chauffe-eau électrique instantané 1, la solution de départ en libérant ainsi CO2 et NH3 , puis, à 50-55 degrés C et avec accélération par la présence de germes cristallins, on fait précipiter en 3, à partir de la solution restante, sous amenée de NH3 , air et H2 O2 , les composés d'uranium (2 NH 4 F.UO4 ) qu'elle renferme et on les oxyde par vapeur d'eau en U3 O8 sans fluor dans un four 6 à 800 degrés C. L'invention intéresse particulièrement le retraitement de l'uranium usagé.
FR7905075A 1978-03-13 1979-02-27 Procede de recuperation de composes d'uranium a partir d'eaux residuaires de la conversion d'uranylcarbonate d'ammonium Withdrawn FR2419907A1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19782810776 DE2810776A1 (de) 1978-03-13 1978-03-13 Verfahren zur wiedergewinnung von uranverbindungen aus bei der auc-konversion entstehenden abwaessern

Publications (1)

Publication Number Publication Date
FR2419907A1 true FR2419907A1 (fr) 1979-10-12

Family

ID=6034269

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7905075A Withdrawn FR2419907A1 (fr) 1978-03-13 1979-02-27 Procede de recuperation de composes d'uranium a partir d'eaux residuaires de la conversion d'uranylcarbonate d'ammonium

Country Status (7)

Country Link
JP (1) JPS54127898A (fr)
BE (1) BE874799A (fr)
DE (1) DE2810776A1 (fr)
ES (1) ES478495A1 (fr)
FR (1) FR2419907A1 (fr)
IT (1) IT1113408B (fr)
SE (1) SE7902137L (fr)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112992396B (zh) * 2020-12-10 2023-12-15 中核二七二铀业有限责任公司 一种煅烧制备核纯级铀氧化物过程中尾气利用装置

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2205482A1 (fr) * 1972-11-06 1974-05-31 Babcock & Wilcox Co
US3842155A (en) * 1969-04-23 1974-10-15 Nukem Gmbh Treatment of waste materials generated in the conversion of uf6 to uo2 by the auc route

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3842155A (en) * 1969-04-23 1974-10-15 Nukem Gmbh Treatment of waste materials generated in the conversion of uf6 to uo2 by the auc route
FR2205482A1 (fr) * 1972-11-06 1974-05-31 Babcock & Wilcox Co

Also Published As

Publication number Publication date
DE2810776A1 (de) 1979-09-20
SE7902137L (sv) 1979-09-14
IT1113408B (it) 1986-01-20
ES478495A1 (es) 1979-11-01
BE874799A (fr) 1979-07-02
IT7920793A0 (it) 1979-03-07
JPS54127898A (en) 1979-10-04

Similar Documents

Publication Publication Date Title
JPS5317566A (en) Denitration method for of exhaust gas
FR2427665A1 (fr) Installation de stockage pour les elements combustibles de reacteurs nucleaires
GB1208089A (en) Improvements in burner-flame arrester for burning off-gas from a boiling water reactor power plant
FR2419907A1 (fr) Procede de recuperation de composes d'uranium a partir d'eaux residuaires de la conversion d'uranylcarbonate d'ammonium
JPS5439791A (en) Operation method of reactor
SE8106708L (sv) Sett att erhalla provstycken fran en radioaktiv reaktorkomponent, nedsenkt i en stralskyddande basseng, samt anordning for genomforande av settet
GB1300216A (en) Nuclear reactor off-gas burner system
JPS5327800A (en) Uranium or/and thorium removingand recovering method from soln. containing uranium or/and thorium
ES8105883A1 (es) Metodo para cambiar los tubos de un generador de vapor
GB1061497A (en) Recovery of uranium and plutonium values from aqueous solutions of ammonium fluoride,particularly from zirflex-type waste solutions
JPS5229597A (en) Control rod of nuclear reactor
JPS5419484A (en) Method of deodorizing sewage
JPS52100082A (en) Pressure suppression device
JPS5327799A (en) Treating system for gas waste in light water type reactor
FR2311754A1 (fr) Procede de dissolution du dioxyde de plutonium
JPS52133498A (en) Separating and recovering method of i/132 from te-132
FR2419908A2 (fr) Procede de recuperation de composes d'uranium a partir d'eaux residuaires de la conversion d'uranylcarbonate d'ammonium
JPS53139098A (en) Nuclear fuel element
JPS53120097A (en) Removing method of tritium
JPS54197A (en) Nuclear fuel element
JPS5436075A (en) Method of treating waste water by way of combustion
JPS5349696A (en) Operation method of reactor
JPS53122090A (en) Reactor pressure vessel
JPS5323573A (en) Thermal oxidation method of semiconductor
JPS52120556A (en) Treating method of aqueous polyvinyl alcohol solution

Legal Events

Date Code Title Description
ST Notification of lapse