GB1256283A - Improvements in the preparation of sintered uranium dioxide grains - Google Patents

Improvements in the preparation of sintered uranium dioxide grains

Info

Publication number
GB1256283A
GB1256283A GB42696/69A GB4269669A GB1256283A GB 1256283 A GB1256283 A GB 1256283A GB 42696/69 A GB42696/69 A GB 42696/69A GB 4269669 A GB4269669 A GB 4269669A GB 1256283 A GB1256283 A GB 1256283A
Authority
GB
United Kingdom
Prior art keywords
uranium
compacts
hydrogen
cooling
uranium dioxide
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
GB42696/69A
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of GB1256283A publication Critical patent/GB1256283A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • 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

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

1,256,283. Uranium dioxide. GENERAL ELECTRIC CO. 27 Aug., 1969 [29 Oct., 1968], No. 42696/69. Heading C1A. Substantially spherical uranium dioxide nuclear fuel grains are made by sintering pressed compacts of uranium dioxde or ammonium diuranate in dry hydrogen at a temperature of at least 1900‹ C. until grains of the desired size are formed, and cooling the compacts in hydrogen or inert gas such that metallic uranium is precipitated at the grain boundaries, and when the temperature has reached about 400‹ C. continuing the cooling in a hydrogen atmosphere such that the precipitated uranium reacts with the hydrogen during cooling to form uranium hydride, causing the compacts to disintegrate into the grains that have been formed. The dry hydrogen used in the sintering is sufficiently dry to reduce the uranium dioxide to substoichiometric form, i.e. UO 2-x where x is up to 0À3. Uranium, or a grain growth accelerator e.g. an oxide of aluminium, beryllium, magnesium or titanium may be added to powdered uranium dioxide or ammonium diuranate before pressing into compacts. A cooling rate of 100- 300‹ C./min. is desirable. When the disintegrated compacts are exposed to air, the uranium hydride is oxidized to uranium dioxide of o/u ratio substantially 2À00. Examples describe the heating of uranium dioxide and ammonium diuranate in molybdenum tubes in an atmosphere of hydrogen having a dew point of-40‹ C., the sintering temperature being 2000-2100‹ C. and the rate of cooling 100-300‹ C./min.
GB42696/69A 1968-10-29 1969-08-27 Improvements in the preparation of sintered uranium dioxide grains Expired GB1256283A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US77164268A 1968-10-29 1968-10-29

Publications (1)

Publication Number Publication Date
GB1256283A true GB1256283A (en) 1971-12-08

Family

ID=25092510

Family Applications (1)

Application Number Title Priority Date Filing Date
GB42696/69A Expired GB1256283A (en) 1968-10-29 1969-08-27 Improvements in the preparation of sintered uranium dioxide grains

Country Status (3)

Country Link
DE (1) DE1953277A1 (en)
FR (1) FR2021808A1 (en)
GB (1) GB1256283A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2860639A1 (en) * 2003-10-06 2005-04-08 Commissariat Energie Atomique Manufacture of nuclear fuel pellets from mixed uranium and plutonium oxide powders employs super-stoichiometric conditions for co-grinding and/or fritting stages

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2860639A1 (en) * 2003-10-06 2005-04-08 Commissariat Energie Atomique Manufacture of nuclear fuel pellets from mixed uranium and plutonium oxide powders employs super-stoichiometric conditions for co-grinding and/or fritting stages

Also Published As

Publication number Publication date
FR2021808A1 (en) 1970-07-24
DE1953277A1 (en) 1970-06-04

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