GB817861A - Separation of fission products from irradiated uranium - Google Patents

Separation of fission products from irradiated uranium

Info

Publication number
GB817861A
GB817861A GB935454A GB935454A GB817861A GB 817861 A GB817861 A GB 817861A GB 935454 A GB935454 A GB 935454A GB 935454 A GB935454 A GB 935454A GB 817861 A GB817861 A GB 817861A
Authority
GB
United Kingdom
Prior art keywords
fission products
heating
separation
uranium
plutonium
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
GB935454A
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
Publication of GB817861A publication Critical patent/GB817861A/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
    • G21C19/48—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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Fission products are separated from neutron-irradiated uranium by heating under vacuum at a temperature above 1130 DEG C. Heating may be carried out electrically in a beryllium oxide crucible. At a temperature of 1250 DEG C. and a pressure of 104 mm. of mercury, fission products, e.g. Sr90 and Cs137, distil off and are collected on a cooled disc or cylinder. By heating the residue to at least 1400 DEG C., plutonium distils and is collected separately. Alternatively, if the original uranium is heated quickly to the higher temperature, fission products and plutonium distil off together and may be separated subsequently.
GB935454A 1953-04-21 1954-03-30 Separation of fission products from irradiated uranium Expired GB817861A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA817861X 1953-04-21

Publications (1)

Publication Number Publication Date
GB817861A true GB817861A (en) 1959-08-06

Family

ID=4172572

Family Applications (1)

Application Number Title Priority Date Filing Date
GB935454A Expired GB817861A (en) 1953-04-21 1954-03-30 Separation of fission products from irradiated uranium

Country Status (1)

Country Link
GB (1) GB817861A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4002316A1 (en) * 1989-01-28 1990-08-02 Doryokuro Kakunenryo METHOD FOR TREATING HIGH RADIOACTIVE WASTE
US5185104A (en) * 1989-01-28 1993-02-09 Doryokuro Kakunenryo Kaihatsu Jigyodan Method of treatment of high-level radioactive waste

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4002316A1 (en) * 1989-01-28 1990-08-02 Doryokuro Kakunenryo METHOD FOR TREATING HIGH RADIOACTIVE WASTE
US5185104A (en) * 1989-01-28 1993-02-09 Doryokuro Kakunenryo Kaihatsu Jigyodan Method of treatment of high-level radioactive waste
DE4002316C2 (en) * 1989-01-28 1998-04-09 Doryokuro Kakunenryo Process for treating a high level radioactive waste

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