GB811790A - Improvements in or relating to vessels for processing nuclear fuel - Google Patents

Improvements in or relating to vessels for processing nuclear fuel

Info

Publication number
GB811790A
GB811790A GB624456A GB624456A GB811790A GB 811790 A GB811790 A GB 811790A GB 624456 A GB624456 A GB 624456A GB 624456 A GB624456 A GB 624456A GB 811790 A GB811790 A GB 811790A
Authority
GB
United Kingdom
Prior art keywords
pillar
nuclear fuel
vessels
relating
pipe
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
GB624456A
Inventor
Ronald Tunstall Ackroyd
Dennis Kenyon
Derek Edmund Abel
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 GB624456A priority Critical patent/GB811790A/en
Publication of GB811790A publication Critical patent/GB811790A/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)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

<PICT:0811790/III/1> A vessel for dissolving irradiated nuclear fuel elements comprises a hollow pillar 10 which is connected at its ends with a container 11, e.g. of annular form, and is surrounded by thermal neutron absorbing and moderating material 31, e.g. borated graphite or cement loaded with borax and wood flour. The fuel elements are lowered through lid 23 into the hollow pillar 10 and nitric acid is fed in through pipe 21. The pillar 10 is then heated by steam jacket 14, setting up circulation of the acid up through the pillar and down through the space 11. When the elements have dissolved, the solution is removed through pipe 17. Condensers may be attached at 19.
GB624456A 1956-02-28 1956-02-28 Improvements in or relating to vessels for processing nuclear fuel Expired GB811790A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB624456A GB811790A (en) 1956-02-28 1956-02-28 Improvements in or relating to vessels for processing nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB624456A GB811790A (en) 1956-02-28 1956-02-28 Improvements in or relating to vessels for processing nuclear fuel

Publications (1)

Publication Number Publication Date
GB811790A true GB811790A (en) 1959-04-15

Family

ID=9811028

Family Applications (1)

Application Number Title Priority Date Filing Date
GB624456A Expired GB811790A (en) 1956-02-28 1956-02-28 Improvements in or relating to vessels for processing nuclear fuel

Country Status (1)

Country Link
GB (1) GB811790A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2449950A1 (en) * 1979-02-20 1980-09-19 Doryokuro Kakunenryo ANNULAR TANK FOR STORING NUCLEAR MATERIAL AND METHOD FOR THE PRODUCTION THEREOF
FR2458879A1 (en) * 1979-06-13 1981-01-02 Nukem Gmbh EXTRACTION COLUMN FOR FISSION MATERIALS AND / OR RAW MATERIALS
EP2266928A1 (en) * 2009-02-20 2010-12-29 Construcciones Tecnicas de Radioterapia, S.L. Mass for manufacturing products with a high neutron radioprotection capacity.

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2449950A1 (en) * 1979-02-20 1980-09-19 Doryokuro Kakunenryo ANNULAR TANK FOR STORING NUCLEAR MATERIAL AND METHOD FOR THE PRODUCTION THEREOF
FR2458879A1 (en) * 1979-06-13 1981-01-02 Nukem Gmbh EXTRACTION COLUMN FOR FISSION MATERIALS AND / OR RAW MATERIALS
EP2266928A1 (en) * 2009-02-20 2010-12-29 Construcciones Tecnicas de Radioterapia, S.L. Mass for manufacturing products with a high neutron radioprotection capacity.

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