GB953977A - Method for preparing uo compacts - Google Patents

Method for preparing uo compacts

Info

Publication number
GB953977A
GB953977A GB12198/62A GB1219862A GB953977A GB 953977 A GB953977 A GB 953977A GB 12198/62 A GB12198/62 A GB 12198/62A GB 1219862 A GB1219862 A GB 1219862A GB 953977 A GB953977 A GB 953977A
Authority
GB
United Kingdom
Prior art keywords
uranium
uranium dioxide
compacting
sintering
pressing
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
GB12198/62A
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.)
Filing date
Publication date
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Publication of GB953977A publication Critical patent/GB953977A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/623Oxide fuels
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

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

Abstract

Uranium dioxide compacts are prepared by adding 2-5% water to highly sinterable uranium dioxide, compacting at at least 3000 p.s.i. and sintering in a reducing atmosphere. After the addition of water the uranium dioxide may be converted to a free flowing powder prior to pressing and sintering by pre-pressing at at least 2500 p.s.i. and comminuting to obtain fine particles. Sintered densities of 99% of the theoretical may be obtained by compacting at 150,000 to 200,000 p.s.i. and firing at 1200 DEG Cl for 8 hours followed by 8 hours at 2000 DEG C. The uranium dioxide may be prepared by precipitating uranium values from an aqueous uranyl fluoride solution at an ammonium/uranium ratio of at least 25 to 1 with thorough agitation, contacting the precipitate with steam at 400-650 DEG C., thus forming U3O8 which is reduced to UO2 with hydrogen at 550-600 DEG C. and re-oxidized until an oxygen/uranium ratio of 2.08-2.13 is obtained. Specification 937,330 is referred to.
GB12198/62A 1961-05-19 1962-03-29 Method for preparing uo compacts Expired GB953977A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US11140561A 1961-05-19 1961-05-19

Publications (1)

Publication Number Publication Date
GB953977A true GB953977A (en) 1964-04-02

Family

ID=22338351

Family Applications (1)

Application Number Title Priority Date Filing Date
GB12198/62A Expired GB953977A (en) 1961-05-19 1962-03-29 Method for preparing uo compacts

Country Status (1)

Country Link
GB (1) GB953977A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3520958A (en) * 1967-10-05 1970-07-21 Reactor Ct Nederland Dev Of Nu Method for preparing an oxidic fissile material containing a metal boride as burnable poison
GB2362497A (en) * 2000-04-04 2001-11-21 Franco Belge Combustibles Granules of nuclear fuel material

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3520958A (en) * 1967-10-05 1970-07-21 Reactor Ct Nederland Dev Of Nu Method for preparing an oxidic fissile material containing a metal boride as burnable poison
GB2362497A (en) * 2000-04-04 2001-11-21 Franco Belge Combustibles Granules of nuclear fuel material
GB2362497B (en) * 2000-04-04 2004-08-11 Franco Belge Combustibles Granules of nuclear fuel material

Similar Documents

Publication Publication Date Title
ES8403426A1 (en) Conversion of uranium hexafluoride to oxides of uranium
GB1146879A (en) Nuclear reactor fuel
GB1349584A (en) Process for producing ammonium diuranate
GB850957A (en) A method of preparing fluoride-free uranium dioxide
GB953977A (en) Method for preparing uo compacts
GB1208433A (en) Manufacture of ceramic artefacts having pores
GB1285190A (en) Improvements in ceramic fissile materials
GB946513A (en) Preparation of spherical uranium dioxide particles
GB978615A (en) Improvements in or relating to the production of fuel materials for nuclear reactors
GB1034505A (en) Improvements in or relating to sintered uranium-plutonium compounds
GB1053786A (en)
GB1365014A (en) Ceramic defluorination and reduction process
US3761546A (en) Method of making uranium dioxide bodies
GB857672A (en) Method of preparing a fuel element for a nuclear reactor
GB1030465A (en) Method of preparation of mixed oxides of actinides
US3168371A (en) Process for producing high density urania fuel elements
GB937330A (en) Preparation of uo for nuclear reactor fuel pellets
GB1142497A (en) A process for recovering uranium from zirconium clad uranium bearing nuclear fuel elements
GB934254A (en) Production of high density sintered uranium oxide
GB1198454A (en) Method for Reprocessing Nuclear Fuel
GB1148228A (en) Improved urania sol forming method
GB1238775A (en)
GB1205169A (en) Improvements in or relating to the processing or irradiated nuclear fuel
GB914154A (en) Improvements in or relating to the production of uranium-carbon alloys
Hart Fabrication of high-density UO2 and (U0. 75Pu0. 25) O2 by hot pressing