GB2004407A – Purification of plutonium
– Google Patents
GB2004407A – Purification of plutonium
– Google Patents
Purification of plutonium
Info
Publication number
GB2004407A
GB2004407A
GB7835179A
GB7835179A
GB2004407A
GB 2004407 A
GB2004407 A
GB 2004407A
GB 7835179 A
GB7835179 A
GB 7835179A
GB 7835179 A
GB7835179 A
GB 7835179A
GB 2004407 A
GB2004407 A
GB 2004407A
Authority
GB
United Kingdom
Prior art keywords
plutonium
uranium
neptunium
aqueous phase
hydroxylamine
Prior art date
1977-09-16
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
GB7835179A
Other versions
GB2004407B
(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.)
British Nuclear Fuels PLC
Original Assignee
British Nuclear Fuels PLC
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.)
1977-09-16
Filing date
1978-08-31
Publication date
1979-03-28
1978-08-31
Application filed by British Nuclear Fuels PLC
filed
Critical
British Nuclear Fuels PLC
1978-08-31
Priority to GB7835179A
priority
Critical
patent/GB2004407B/en
1979-03-28
Publication of GB2004407A
publication
Critical
patent/GB2004407A/en
1982-03-03
Application granted
granted
Critical
1982-03-03
Publication of GB2004407B
publication
Critical
patent/GB2004407B/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
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
G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
C—CHEMISTRY; METALLURGY
C01—INORGANIC CHEMISTRY
C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C01G56/00—Compounds of transuranic elements
C01G56/001—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
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
C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
C22B60/026—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
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
C22B60/0295—Obtaining thorium, uranium, or other actinides obtaining other actinides except 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
C22B60/04—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
Abstract
The plutonium in a plutonium- containing stream obtained in the reprocessing of irradiated nuclear fuel is separated from neptunium and uranium by bringing a solution containing plutonium, neptunium and uranium in an organic solvent into contact first with an aqueous solution of a hydroxylamine and/or a hydrazine salt at 30 to 35 DEG C to preferentially reduce the neptunium and to extract it into the aqueous phase and then bringing the organic solution containing plutonium and uranium into contact with an aqueous phase containing a hydroxylamine and a hydrazine salt at about 50 DEG C to preferentially reduce the plutonium and to extract it into the aqueous phase leaving the uranium in the organic solvent.
GB7835179A
1977-09-16
1978-08-31
Purification of plutonium
Expired
GB2004407B
(en)
Priority Applications (1)
Application Number
Priority Date
Filing Date
Title
GB7835179A
GB2004407B
(en)
1977-09-16
1978-08-31
Purification of plutonium
Applications Claiming Priority (2)
Application Number
Priority Date
Filing Date
Title
GB3878677
1977-09-16
GB7835179A
GB2004407B
(en)
1977-09-16
1978-08-31
Purification of plutonium
Publications (2)
Publication Number
Publication Date
GB2004407A
true
GB2004407A
(en)
1979-03-28
GB2004407B
GB2004407B
(en)
1982-03-03
Family
ID=26263911
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB7835179A
Expired
GB2004407B
(en)
1977-09-16
1978-08-31
Purification of plutonium
Country Status (1)
Country
Link
GB
(1)
GB2004407B
(en)
Cited By (6)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
FR2640888A1
(en)
*
1988-12-24
1990-06-29
Kernforschungsz Karlsruhe
WO1999022379A1
(en)
*
1997-10-25
1999-05-06
British Nuclear Fuels Plc
Nuclear fuel reprocessing
WO2000013188A1
(en)
*
1998-08-28
2000-03-09
British Nuclear Fuels Plc
Nuclear fuel processing including reduction of np(vi) to np(v) with a hydrophilic substituted hydroxylamine
WO2000013187A1
(en)
*
1998-08-28
2000-03-09
British Nuclear Fuels Plc
Nuclear fuel reprocessing including reduction of np(vi) to np(v) with an oxime
WO2002073629A1
(en)
*
2001-03-13
2002-09-19
Commissariat A L’energie Atomique
Method for decontaminating solid iodine filters
WO2007135178A1
(en)
*
2006-05-24
2007-11-29
Commissariat A L’energie Atomique
Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
Families Citing this family (1)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
RU2756277C1
(en)
*
2021-03-04
2021-09-30
Федеральное государственное бюджетное учреждение “Петербургский институт ядерной физики им. Б.П. Константинова Национального исследовательского центра “Курчатовский институт”
Method for chemical enrichment of uranium with light isotopes
1978
1978-08-31
GB
GB7835179A
patent/GB2004407B/en
not_active
Expired
Cited By (16)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
FR2640888A1
(en)
*
1988-12-24
1990-06-29
Kernforschungsz Karlsruhe
WO1999022379A1
(en)
*
1997-10-25
1999-05-06
British Nuclear Fuels Plc
Nuclear fuel reprocessing
WO2000013188A1
(en)
*
1998-08-28
2000-03-09
British Nuclear Fuels Plc
Nuclear fuel processing including reduction of np(vi) to np(v) with a hydrophilic substituted hydroxylamine
WO2000013187A1
(en)
*
1998-08-28
2000-03-09
British Nuclear Fuels Plc
Nuclear fuel reprocessing including reduction of np(vi) to np(v) with an oxime
US6413482B1
(en)
1998-08-28
2002-07-02
British Nuclear Fuels Plc
Method for reprocessing nuclear fuel by employing oximes
US6444182B1
(en)
1998-08-28
2002-09-03
British Nuclear Fuels Plc
Nuclear fuel reprocessing using hydrophilic substituted hydroxylamines
WO2002073629A1
(en)
*
2001-03-13
2002-09-19
Commissariat A L’energie Atomique
Method for decontaminating solid iodine filters
FR2822287A1
(en)
*
2001-03-13
2002-09-20
Commissariat Energie Atomique
PROCESS FOR DECONTAMINATION OF SOLID IODINE FILTERS
GB2390219A
(en)
*
2001-03-13
2003-12-31
Commissariat Energie Atomique
Method for decontaminating solid iodine filters
GB2390219B
(en)
*
2001-03-13
2004-10-27
Commissariat Energie Atomique
Method for decontaminating solid iodine filters
US7101822B2
(en)
2001-03-13
2006-09-05
Commissariat A L’energie Atomique
Method for decontaminating solid iodine filters
WO2007135178A1
(en)
*
2006-05-24
2007-11-29
Commissariat A L’energie Atomique
Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
FR2901627A1
(en)
*
2006-05-24
2007-11-30
Commissariat Energie Atomique
Recycling of used nuclear fuel and making of mixed oxide of uranium and plutonium comprises e.g. separating uranium and plutonium from aqueous nitric solution containing fuel, purifying and co-converting plutonium and uranium in to oxide
US7887767B2
(en)
*
2006-05-24
2011-02-15
Commissariat A L’energie Atomique
Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
CN101449338B
(en)
*
2006-05-24
2012-10-24
原子能委员会
Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
KR101386696B1
(en)
2006-05-24
2014-04-18
아레바 엔씨
Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
Also Published As
Publication number
Publication date
GB2004407B
(en)
1982-03-03
Similar Documents
Publication
Publication Date
Title
GB834529A
(en)
1960-05-11
Separation of plutonium from neutron-irradiated uranium
ES368454A1
(en)
1972-01-01
Irradiated fuel recovery system
GB2004407A
(en)
1979-03-28
Purification of plutonium
BE605763A
(en)
1961-11-03
Process for the recovery of plutonium from uranium fuel bombarded by neutrons
ES237011A1
(en)
1958-05-16
Process for separation of protactinium,thorium and uranium from neutronirradiated thorium
GB1084642A
(en)
1967-09-27
Improvements in irradiated nuclear fuel recovery
GB1452115A
(en)
1976-10-13
Method of selective stripping of plutonium for organic solvents loaded with plutonium
GB850957A
(en)
1960-10-12
A method of preparing fluoride-free uranium dioxide
GB1330535A
(en)
1973-09-19
Processing of irradiated nuclear reactor fuel
GB1260096A
(en)
1972-01-12
Organic phase reduction of uranium
GB892891A
(en)
1962-04-04
Improvements in or relating to nuclear reactors
GB1156366A
(en)
1969-06-25
Process for the Separation of Molybdenum in Solution
FR2304994A1
(en)
1976-10-15
PYROCHEMICAL SEPARATION OF PLUTONIUM FROM IRRADIATED NUCLEAR FUELS, BY THERMAL DECOMPOSITION IN MOLTEN NITRATES
GB1164980A
(en)
1969-09-24
Process for Depleting <283>PuO2 in <17>O and <18>O.
GB1205169A
(en)
1970-09-16
Improvements in or relating to the processing or irradiated nuclear fuel
GB1304313A
(en)
1973-01-24
GB1536335A
(en)
1978-12-20
Uranium plutonium and neptunium(iv)sulphite tetrahydrates their preparation and a process for the preparation of an actinide dioxide
CA576900A
(en)
1959-06-02
Solvent extraction of nitrate solutions of neutron irradiated uranium
GB801743A
(en)
1958-09-17
Extraction of plutonium and uranium
GB1142497A
(en)
1969-02-05
A process for recovering uranium from zirconium clad uranium bearing nuclear fuel elements
JPS52137600A
(en)
1977-11-17
Tritium in waste water removing method in atomic energy plant
GB879041A
(en)
1961-10-04
Improvements in or relating to the processing of nuclear reactor fuel elements
GB1207288A
(en)
1970-09-30
Process for the liquid-liquid extraction of uranium and plutonium
JPS53144788A
(en)
1978-12-16
Obtaining method of space dose from atomic power facilities
JPS5241795A
(en)
1977-03-31
Atomic reactor
Legal Events
Date
Code
Title
Description
1987-04-15
PCNP
Patent ceased through non-payment of renewal fee
