GB1079901A - Improvements in or relating to the processing of irradiated nuclear fuels - Google Patents

Improvements in or relating to the processing of irradiated nuclear fuels

Info

Publication number
GB1079901A
GB1079901A GB2599563A GB2599563A GB1079901A GB 1079901 A GB1079901 A GB 1079901A GB 2599563 A GB2599563 A GB 2599563A GB 2599563 A GB2599563 A GB 2599563A GB 1079901 A GB1079901 A GB 1079901A
Authority
GB
United Kingdom
Prior art keywords
relating
processing
nitric acid
strontium
nuclear fuels
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
GB2599563A
Inventor
Herman John De Nordwall
Thomas Victor Healy
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB2599563A priority Critical patent/GB1079901A/en
Publication of GB1079901A publication Critical patent/GB1079901A/en
Expired 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
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Compounds Of Alkaline-Earth Elements, Aluminum Or Rare-Earth Metals (AREA)

Abstract

Strontium-90 is extracted from fission product solutions by adding nitric acid to make the solution 15-17 N, thereby precipitating the nitrates of strontium and barium, and then treating the precipitate with dilute nitric acid to leach out strontium nitrate. Precipitation may be effected at 55 DEG C. and the precipitate then dissolved and reprecipitated at 35 DEG C. The solution used for leaching out the strontum nitrate may be 5 N in nitric acid. Reference has been directed by the Comptroller to Specification 844,376.
GB2599563A 1963-07-01 1963-07-01 Improvements in or relating to the processing of irradiated nuclear fuels Expired GB1079901A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB2599563A GB1079901A (en) 1963-07-01 1963-07-01 Improvements in or relating to the processing of irradiated nuclear fuels

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2599563A GB1079901A (en) 1963-07-01 1963-07-01 Improvements in or relating to the processing of irradiated nuclear fuels

Publications (1)

Publication Number Publication Date
GB1079901A true GB1079901A (en) 1967-08-16

Family

ID=10236657

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2599563A Expired GB1079901A (en) 1963-07-01 1963-07-01 Improvements in or relating to the processing of irradiated nuclear fuels

Country Status (1)

Country Link
GB (1) GB1079901A (en)

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