ES8104971A2 - Procedimiento para la recuperacion de cumpuestos de uranio - Google Patents

Procedimiento para la recuperacion de cumpuestos de uranio

Info

Publication number
ES8104971A2
ES8104971A2 ES478617A ES47861779A ES8104971A2 ES 8104971 A2 ES8104971 A2 ES 8104971A2 ES 478617 A ES478617 A ES 478617A ES 47861779 A ES47861779 A ES 47861779A ES 8104971 A2 ES8104971 A2 ES 8104971A2
Authority
ES
Spain
Prior art keywords
cpds
degrees
soln
pptn
recovery
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
ES478617A
Other languages
English (en)
Other versions
ES478617A0 (es
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 ES478617A0 publication Critical patent/ES478617A0/es
Publication of ES8104971A2 publication Critical patent/ES8104971A2/es
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/01Oxides; Hydroxides
    • C01G43/025Uranium dioxide
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/01Oxides; Hydroxides
    • 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

Landscapes

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

Abstract

PROCEDIMIENTO PARA LA RECUPERACION DE COMPUESTOS DE URANIO, CUANDO ESTAS SOLUCIONES CONTIENEN NITRATO AMONICO Y TAMBIEN OXIDO NITRICO. EN PRIMER LUGAR SE APLICA EL PROCEDIMIENTO DE SEPARACION DE LA PATENTE PRINCIPAL PARA EL ANHIDRIDO CARBONICO, AMONIACO Y AGUA. UNA VEZ HECHO ESTO LA SOLUCION RESTANTE SE EVACUA EN UN DEPOSITO DE CRISTALIZACION CON CRISTALES DEL PRODUCTO DE PRECIPITACION, MANTENIENDOSE ENTRE 50 Y 55GC. SE DOSIFICAN CONSECUTIVAMENTE (I) Y (II) MANTENIENDO EL PH ENTRE 5,6 Y 5,9 MEDIANTE ADICION REGULADA DE (III). A CONTINUACION SE ALMACENA EL COMPUESTO DE ADICION PRECIPITADO. ESTE CONTIENE MENOS DE 20 MG./L DE PEROXIDO DE URANIO Y NITRATO AMONICO, PUDIENDO CONTENER TAMBIEN PRODUCTOS SUBSIGUIENTES DE LA DESCOMPOSICION DE URANIO. (I) HNO3; (II) H2O2; (III) HN3.
ES478617A 1978-03-16 1979-03-14 Procedimiento para la recuperacion de cumpuestos de uranio Expired ES8104971A2 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2811559 1978-03-16

Publications (2)

Publication Number Publication Date
ES478617A0 ES478617A0 (es) 1981-04-16
ES8104971A2 true ES8104971A2 (es) 1981-04-16

Family

ID=6034652

Family Applications (1)

Application Number Title Priority Date Filing Date
ES478617A Expired ES8104971A2 (es) 1978-03-16 1979-03-14 Procedimiento para la recuperacion de cumpuestos de uranio

Country Status (6)

Country Link
JP (1) JPS54128495A (es)
BE (1) BE874886R (es)
ES (1) ES8104971A2 (es)
FR (1) FR2419908A2 (es)
IT (1) IT1163654B (es)
SE (1) SE7902141L (es)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP3119943B2 (ja) * 1992-07-01 2000-12-25 プレストーン、プロダクツ、コーポレーション 循環不凍液/冷却剤の再腐食防止方法および再腐食防止剤

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1335272A (fr) * 1962-09-06 1963-08-16 Nukem Gmbh Procédé pour la fabrication de poudre de dioxyde d'uranium ainsi que les produits conformes ou similaires à ceux obtenus par ce procédé
DE1920479A1 (de) * 1969-04-23 1970-11-19 Nukem Gmbh Filtrat- und Gasaufbereitung
DE2057966A1 (de) * 1970-11-25 1972-06-08 Nukem Gmbh Verfahren zur Wiedergewinnung von Uranverbindungen,Ammoniak,Kohlendioxid und Wasser
US3980757A (en) * 1972-11-06 1976-09-14 The Babcock & Wilcox Company Process for uranium separation and preparation of UO4.2NH3.2HF
DE2623977C3 (de) * 1976-05-28 1979-04-12 Nukem Gmbh, 6450 Hanau Verfahren und Vorrichtung zur Herstellung von rieselfähigem, direkt verpressbarem Urandioxid-Pulver

Also Published As

Publication number Publication date
ES478617A0 (es) 1981-04-16
FR2419908A2 (fr) 1979-10-12
JPS54128495A (en) 1979-10-05
IT7920857A0 (it) 1979-03-09
BE874886R (fr) 1979-07-16
SE7902141L (sv) 1979-09-17
IT1163654B (it) 1987-04-08

Similar Documents

Publication Publication Date Title
GB1273945A (en) Pulsed laser-ignited thermonuclear reactor
JPS5413653A (en) Air dehumidifying method
ES8104971A2 (es) Procedimiento para la recuperacion de cumpuestos de uranio
JPS529963A (en) Method for removing arsenic and silicic acid contained in aqueous solu tion simultaneously
JPS541786A (en) Fuel exchanging method for boiling water reactor
GB1164980A (en) Process for Depleting <283>PuO2 in <17>O and <18>O.
JPS5437951A (en) Manufacturing method of water boiler heat exchanger
JPS52155882A (en) Process and apparatus for stabilizing output of combination plant of gas turbine,
JPS5267487A (en) Automatic starting apparatus for nuclear reactor
JPS5387085A (en) Method of shot peening
JPS524986A (en) Pressure tube type reactor
JPS53128234A (en) Input system of sentence information
JPS5367673A (en) Exchanging method for window foil of incidence window of reactor fortreating exhaust gas irradiated with radioactive rays
JPS5217145A (en) Process and device for recovering power using waste heat of condenser of power plant
JPS5390544A (en) Output control method for power plant using extraction turbine
JPS53120100A (en) Decomposition method of nitric acid and or nitric acid ion
JPS544889A (en) Converting method for h type cation exchange resin into ca type one
JPS52107452A (en) Operation of steam turbine by controlled pressure
JPS52104694A (en) Division rate controlling device for thermal medium
JPS51151493A (en) Nuclear power plant superheater s team temperature control system
GB1157786A (en) Method of Removing Radioiodine Values from a Gaseous Medium
JPS529798A (en) Nuclear power plant
JPS5399190A (en) Plenum device
JPS53148074A (en) Geo-thermal generation system
JPS5237601A (en) Steam generator control system