GB1048802A – Pyrohydrolysis of carbide-type nuclear fuels
– Google Patents
GB1048802A – Pyrohydrolysis of carbide-type nuclear fuels
– Google Patents
Pyrohydrolysis of carbide-type nuclear fuels
Info
Publication number
GB1048802A
GB1048802A
GB737365A
GB737365A
GB1048802A
GB 1048802 A
GB1048802 A
GB 1048802A
GB 737365 A
GB737365 A
GB 737365A
GB 737365 A
GB737365 A
GB 737365A
GB 1048802 A
GB1048802 A
GB 1048802A
Authority
GB
United Kingdom
Prior art keywords
carbide
free
steam
carbon
pyrohydrolysis
Prior art date
1964-04-08
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
GB737365A
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.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
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.)
1964-04-08
Filing date
1965-02-19
Publication date
1966-11-23
1965-02-19
Application filed by US Atomic Energy Commission (AEC)
filed
Critical
US Atomic Energy Commission (AEC)
1966-11-23
Publication of GB1048802A
publication
Critical
patent/GB1048802A/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
C—CHEMISTRY; METALLURGY
C01—INORGANIC CHEMISTRY
C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
C01B13/00—Oxygen; Ozone; Oxides or hydroxides in general
C01B13/14—Methods for preparing oxides or hydroxides in general
C01B13/32—Methods for preparing oxides or hydroxides in general by oxidation or hydrolysis of elements or compounds in the liquid or solid state or in non-aqueous solution, e.g. sol-gel process
C01B13/322—Methods for preparing oxides or hydroxides in general by oxidation or hydrolysis of elements or compounds in the liquid or solid state or in non-aqueous solution, e.g. sol-gel process of elements or compounds in the solid state
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
C01G43/01—Oxides; Hydroxides
C—CHEMISTRY; METALLURGY
C01—INORGANIC CHEMISTRY
C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C01G43/00—Compounds of uranium
C01G43/01—Oxides; Hydroxides
C01G43/025—Uranium dioxide
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
C01G56/005—Oxides; Hydroxides
C—CHEMISTRY; METALLURGY
C01—INORGANIC CHEMISTRY
C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C01G99/00—Subject matter not provided for in other groups of this subclass
C01G99/006—Compounds containing, besides a metal not provided for elsewhere in this subclass, two or more other elements other than oxygen or hydrogen
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
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
Carbides of uranium and thorium are hydrolysed by contacting with oxygen free steam at from 700 DEG C. to a temperature below that at which the resultant metal oxide sinters, e.g. not exceeding 1150 DEG C., to produce a carbon-free oxide powder. The carbide may be in the form of nuclear fuel elements in which the carbide is encased in a protective metal cladding, this is partially removed to expose the carbide and steam at 700 DEG to 800 DEG C. is used. Alternatively the carbide nuclear fuel may be carbon coated or dispersed in a graphite matrix in which case steam at 1000 DEG to 1150 DEG C. is necessary for complete conversion to the oxide. The product is a free-running, carbon-free oxide powder which is suitable for the partition of unburned fuel, transmutation and fission products by solvent extraction or distillation processes.
GB737365A
1964-04-08
1965-02-19
Pyrohydrolysis of carbide-type nuclear fuels
Expired
GB1048802A
(en)
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
US35838764
US3278278A
(en)
1964-04-08
1964-04-08
Pyrohydrolysis of carbide-type nuclear fuels
Publications (1)
Publication Number
Publication Date
GB1048802A
true
GB1048802A
(en)
1966-11-23
Family
ID=23409462
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB737365A
Expired
GB1048802A
(en)
1964-04-08
1965-02-19
Pyrohydrolysis of carbide-type nuclear fuels
Country Status (5)
Country
Link
US
(1)
US3278278A
(en)
BE
(1)
BE662228A
(en)
DE
(1)
DE1253256B
(en)
GB
(1)
GB1048802A
(en)
SE
(1)
SE311640B
(en)
Families Citing this family (2)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
LU78352A1
(en)
*
1977-10-20
1979-06-01
Euratom
DRY CHEMICAL PROCESS FOR THE RECOVERY OF ACTINIDE METALS
US9623371B1
(en)
2015-09-28
2017-04-18
Savannah River Nuclear Solutions, Llc
Low temperature vapor phase digestion of graphite
Family Cites Families (2)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
GB997355A
(en)
*
1961-01-18
1965-07-07
Atomenergi Ab
Improvements relating to the treatment of spent fuel elements from atomic reactors
FR1314141A
(en)
*
1962-01-16
1963-01-04
Atomenergi Ab
Treatment of spent fuel elements from atomic reactors
1964
1964-04-08
US
US35838764
patent/US3278278A/en
not_active
Expired – Lifetime
1965
1965-02-19
GB
GB737365A
patent/GB1048802A/en
not_active
Expired
1965-03-04
DE
DEU11494A
patent/DE1253256B/en
active
Pending
1965-04-01
SE
SE420565A
patent/SE311640B/xx
unknown
1965-04-08
BE
BE662228D
patent/BE662228A/xx
unknown
Also Published As
Publication number
Publication date
DE1253256B
(en)
1967-11-02
BE662228A
(en)
1965-08-02
SE311640B
(en)
1969-06-23
US3278278A
(en)
1966-10-11
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