GB1084642A – Improvements in irradiated nuclear fuel recovery
– Google Patents
GB1084642A – Improvements in irradiated nuclear fuel recovery
– Google Patents
Improvements in irradiated nuclear fuel recovery
Info
Publication number
GB1084642A
GB1084642A
GB203766A
GB203766A
GB1084642A
GB 1084642 A
GB1084642 A
GB 1084642A
GB 203766 A
GB203766 A
GB 203766A
GB 203766 A
GB203766 A
GB 203766A
GB 1084642 A
GB1084642 A
GB 1084642A
Authority
GB
United Kingdom
Prior art keywords
solution
aqueous solution
uranium
organic
plutonium
Prior art date
1965-02-10
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
GB203766A
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.)
General Electric Co
Original Assignee
General Electric Co
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.)
1965-02-10
Filing date
1966-01-17
Publication date
1967-09-27
1966-01-17
Application filed by General Electric Co
filed
Critical
General Electric Co
1967-09-27
Publication of GB1084642A
publication
Critical
patent/GB1084642A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
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
G21F9/04—Treating liquids
G21F9/06—Processing
G21F9/12—Processing by absorption; by adsorption; by ion-exchange
G21F9/125—Processing by absorption; by adsorption; by ion-exchange by solvent extraction
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
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
An aqueous solution of irradiated uranium nuclear fuel is extracted with a solution of a tertiary or quaternary amine salt in an inert organic diluent to produce an organic extract containing the plutonium and an aqueous solution containing the uranium and fission products; plutonium is stripped from the organic solution, while the aqueous solution is dehydrated and fluorinated, the uranium fluoride being separated from fission product fluorides. Spent UO2 fuel clad in zirconium is dissolved in nitric acid and the solution extracted with a kerosene solution of trilaurylamine nitrate or the quaternary amine nitrate C6H5CH2N(CH3)2 -C12H23NO3. Other suitable organic diluents are xylene, CCl4, and nitromethane; the solution may contain a small amount of n-octyl alcohol. The aqueous solution containing U and fission products and free from Pu is evaporated and calcined, nitrous fumes given off being absorbed to re-form concentrated HNO3. The oxide residue may be fluorinated in the fluidized state either with hydrogen fluoride and fluorine in succession or with fluorine alone. The UF6 is separated from fission product fluorides by fractional distillation or by absorption on granular NaF.
GB203766A
1965-02-10
1966-01-17
Improvements in irradiated nuclear fuel recovery
Expired
GB1084642A
(en)
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
US43168465
US3359078A
(en)
1965-02-10
1965-02-10
Irradaiated nuclear fuel recovery
Publications (1)
Publication Number
Publication Date
GB1084642A
true
GB1084642A
(en)
1967-09-27
Family
ID=23712997
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB203766A
Expired
GB1084642A
(en)
1965-02-10
1966-01-17
Improvements in irradiated nuclear fuel recovery
Country Status (6)
Country
Link
US
(1)
US3359078A
(en)
CH
(1)
CH470731A
(en)
DE
(1)
DE1592418B2
(en)
ES
(1)
ES322748A1
(en)
GB
(1)
GB1084642A
(en)
NL
(1)
NL6601524A
(en)
Cited By (1)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
GB2118759A
(en)
*
1982-03-15
1983-11-02
Euratom
Process for the recovery of plutonium from aqueous nitric solutions
Families Citing this family (11)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
FR2091897B1
(en)
*
1970-04-08
1973-08-10
Commissariat Energie Atomique
US4188361A
(en)
*
1978-04-12
1980-02-12
Davy International (Oil And Chemicals) Limited
Recovery of uranium values
US5000927A
(en)
*
1989-03-31
1991-03-19
General Electric Company
Method of regulating a purex solvent extraction process
JP4312969B2
(en)
*
2001-03-02
2009-08-12
東京電力株式会社
Reprocessing method of spent nuclear fuel
US6605158B1
(en)
2001-10-12
2003-08-12
Bobolink, Inc.
Radioactive decontamination and translocation method
GB201016935D0
(en)
*
2010-10-07
2010-11-24
Mallinckrodt Inc
Extraction process
US9382632B2
(en)
2013-06-21
2016-07-05
Savannah River Nuclear Solutions, Llc
Electrochemical fluorination for processing of used nuclear fuel
US11557404B2
(en)
2013-08-23
2023-01-17
Global Energy Research Associates, LLC
Method of using nanofuel in a nanofuel internal engine
CN112941346A
(en)
*
2019-12-10
2021-06-11
中国科学院大连化学物理研究所
Diluent and preparation and application thereof
CN112614604B
(en)
*
2020-11-26
2022-10-21
中国辐射防护研究院
Pulse extraction column organic phase ignition accident source item estimation method
CN114684843B
(en)
*
2020-12-25
2023-11-03
中核四0四有限公司
Method for rapidly oxidizing oxalic acid
Family Cites Families (4)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
US2837401A
(en)
*
1948-11-04
1958-06-03
Schubert Jack
Separation of plutonium from aqueous solutions by ion-exchange
US3154377A
(en)
*
1960-08-17
1964-10-27
Commissariat Energie Atomique
Process for obtaining plutonium in the form of a concentrated solution
US3046089A
(en)
*
1961-02-08
1962-07-24
Martin J Steindler
Process of treating uranium hexafluoride and plutonium hexafluoride mixtures with sulfur tetrafluoride to separate same
NL301862A
(en)
*
1962-12-26
1900-01-01
1965
1965-02-10
US
US43168465
patent/US3359078A/en
not_active
Expired – Lifetime
1966
1966-01-17
GB
GB203766A
patent/GB1084642A/en
not_active
Expired
1966-02-07
NL
NL6601524A
patent/NL6601524A/xx
unknown
1966-02-08
ES
ES0322748A
patent/ES322748A1/en
not_active
Expired
1966-02-08
DE
DE19661592418
patent/DE1592418B2/en
active
Pending
1966-02-10
CH
CH186966A
patent/CH470731A/en
not_active
IP Right Cessation
Cited By (1)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
GB2118759A
(en)
*
1982-03-15
1983-11-02
Euratom
Process for the recovery of plutonium from aqueous nitric solutions
Also Published As
Publication number
Publication date
CH470731A
(en)
1969-03-31
NL6601524A
(en)
1966-08-11
ES322748A1
(en)
1967-03-16
DE1592418B2
(en)
1976-09-23
DE1592418A1
(en)
1970-12-17
US3359078A
(en)
1967-12-19
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None