DE3009077C2 - - Google Patents

Info

Publication number
DE3009077C2
DE3009077C2 DE19803009077 DE3009077A DE3009077C2 DE 3009077 C2 DE3009077 C2 DE 3009077C2 DE 19803009077 DE19803009077 DE 19803009077 DE 3009077 A DE3009077 A DE 3009077A DE 3009077 C2 DE3009077 C2 DE 3009077C2
Authority
DE
Germany
Prior art keywords
melt
nitric acid
introducing
steps
dissolving
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
Application number
DE19803009077
Other languages
German (de)
English (en)
Other versions
DE3009077A1 (de
Inventor
Fritz Dr. 6450 Hanau De Herrmann
Friedrich Wilhelm Dr. 6457 Maintal De Ledebrink
Wolfgang 6331 Waldsolms De Rosenkranz
Christian 6752 Mainaschaff De Ost
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.)
Siemens AG
Original Assignee
Alkem 6450 Hanau De 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 Alkem 6450 Hanau De GmbH filed Critical Alkem 6450 Hanau De GmbH
Priority to DE19803009077 priority Critical patent/DE3009077A1/de
Publication of DE3009077A1 publication Critical patent/DE3009077A1/de
Application granted granted Critical
Publication of DE3009077C2 publication Critical patent/DE3009077C2/de
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48—Non-aqueous processes
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01F—COMPOUNDS OF THE METALS BERYLLIUM, MAGNESIUM, ALUMINIUM, CALCIUM, STRONTIUM, BARIUM, RADIUM, THORIUM, OR OF THE RARE-EARTH METALS
    • C01F15/00—Compounds of thorium
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/004—Compounds of plutonium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0208—Obtaining thorium, uranium, or other actinides obtaining uranium preliminary treatment of ores or scrap
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0291—Obtaining thorium, uranium, or other actinides obtaining thorium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/04—Obtaining plutonium
    • 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Manufacturing & Machinery (AREA)
  • Environmental & Geological Engineering (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Inorganic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
DE19803009077 1980-03-10 1980-03-10 Verfahren zum aufloesen schwerloeslicher schwermetalloxide Granted DE3009077A1 (de)

Priority Applications (1)

Application Number Priority Date Filing Date Title
DE19803009077 DE3009077A1 (de) 1980-03-10 1980-03-10 Verfahren zum aufloesen schwerloeslicher schwermetalloxide

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19803009077 DE3009077A1 (de) 1980-03-10 1980-03-10 Verfahren zum aufloesen schwerloeslicher schwermetalloxide

Publications (2)

Publication Number Publication Date
DE3009077A1 DE3009077A1 (de) 1981-09-24
DE3009077C2 true DE3009077C2 (OSRAM) 1987-06-11

Family

ID=6096716

Family Applications (1)

Application Number Title Priority Date Filing Date
DE19803009077 Granted DE3009077A1 (de) 1980-03-10 1980-03-10 Verfahren zum aufloesen schwerloeslicher schwermetalloxide

Country Status (1)

Country Link
DE (1) DE3009077A1 (OSRAM)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
PL217150B1 (pl) * 2010-03-26 2014-06-30 Inst Chemii I Techniki Jądrowej Sposób rozpuszczania tlenku toru

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2951510A1 (de) * 1979-12-20 1981-07-02 Alkem Gmbh, 6450 Hanau Verfahren zur aufloesung von schwerloeslichen kernbrennstoffen

Also Published As

Publication number Publication date
DE3009077A1 (de) 1981-09-24

Similar Documents

Publication Publication Date Title
US4056482A (en) Method for preparing aqueous, radioactive waste solutions from nuclear plants for solidification
US3374068A (en) Irradiated fuel reprocessing
DE2855821A1 (de) Verfahren zur wiedergewinnung von palladium und technetium
DE1929512A1 (de) Aufarbeitungssystem fuer bestrahlten Kernbrennstoff
DE2909401A1 (de) Pyroelektrochemisches verfahren zur wiederaufbereitung zerstrahlter kernbrennstoffe
DE1592418B2 (de) Verfahren zur aufarbeitung waessriger loesungen bestrahlter reaktorbrennstoffe
EP0054607A1 (de) Verfahren zur Entfernung von Ammoniumnitrat aus wässrigen Lösungen
DE68916135T2 (de) Verfahren zur Behandlung von verbrauchtem Brennstoff.
EP0170795B1 (de) Verfahren zur Rückgewinnung von Uran-Werten in einem extraktiven Wiederaufarbeitungsprozess für bestrahlte Kernbrennstoffe
DE2758408A1 (de) Verfahren zur abtrennung von spaltprodukten
DE2641492A1 (de) Verfahren zur beladung eines schwach sauren ionenaustauschharzes mit uran
DE1592541A1 (de) Fluessigkeits-Fluessigkeits-Extraktionsverfahren zum Abtrennen des Plutoniums von Uran
DE3642841C2 (OSRAM)
DE3345199C2 (OSRAM)
DE1159920B (de) Verfahren zur Trennung von Uranoxyden von den Oxyden des Thoriums und bzw. oder des Plutoniums
DE1567867A1 (de) Verfahren zur Gewinnung von Metallfluoriden
DE3009077A1 (de) Verfahren zum aufloesen schwerloeslicher schwermetalloxide
DE1467313A1 (de) Verfahren zur Trennung von Uran und Plutonium
US2885260A (en) Method for decontamination of reactor solutions
DE2617968C3 (de) Verfahren zur Aufarbeitung von bei der Herstellung von Brenn- und/oder Brutstoffen für Kernreaktoren anfallender Ammoniumnitratlösung
EP0589076B1 (de) Verfahren zum Herstellen von UO2-oder U/PuO2-Pulver
DE3708751C2 (de) Verfahren zur nassen Auflösung von Uran-Plutonium-Mischoxid-Kernbrennstoffen
DE1150369B (de) Verfahren zum UEberfuehren von Zirkonium und Uran enthaltenden Massen in bestaendige Loesungen
DE3101505C2 (de) Verfahren zum Behandeln von Plutoniumnitrat, gegebenenfalls zusammen mit Uranylnitrat
DE2057760A1 (de) Verfahren zur verbesserten Spaltproduktabtrennung bei der waessrigen Wiederaufarbeitung von abgebrannten Kernbrennstoffen

Legal Events

Date Code Title Description
OM8 Search report available as to paragraph 43 lit. 1 sentence 1 patent law
8110 Request for examination paragraph 44
D2 Grant after examination
8364 No opposition during term of opposition
8320 Willingness to grant licences declared (paragraph 23)
8327 Change in the person/name/address of the patent owner

Owner name: SIEMENS AG, 1000 BERLIN UND 8000 MUENCHEN, DE

8339 Ceased/non-payment of the annual fee