GB1320266A - Sintering process - Google Patents

Sintering process

Info

Publication number
GB1320266A
GB1320266A GB2514571*A GB2514571A GB1320266A GB 1320266 A GB1320266 A GB 1320266A GB 2514571 A GB2514571 A GB 2514571A GB 1320266 A GB1320266 A GB 1320266A
Authority
GB
United Kingdom
Prior art keywords
pellets
uranium dioxide
hydrogen
stoichiometric
april
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
GB2514571*A
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.)
Australian Atomic Energy Commission
Original Assignee
Australian Atomic Energy Commission
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 Australian Atomic Energy Commission filed Critical Australian Atomic Energy Commission
Publication of GB1320266A publication Critical patent/GB1320266A/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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/80—Compositional purity
    • 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

Abstract

1320266 Sintering process for production of uranium dioxide pellets AUSTRALIAN ATOMIC ENERGY COMMISSION 19 April 1971 [9 April 1970] 25145/71 Heading C1A Pellets of stoichiometric uranium dioxide are produced in a process which comprises sintering cold-pressed pellets of non-stoichiometric uranium dioxide having a O : U atomic ratio greater than 2 by heating the pellets in a flowing atmosphere of nitrogen containing from 5,000 to 30,000 p.p.m. of water and from 1 to 10% by volume of hydrogen at a temperature of at least 900‹ C. and thereafter allowing the pellets to cool in a cooling atmosphere containing from 1 to 5% by volume of hydrogen, the total throughout of hydrogen during sintering being not less than the theoretical amount required to reduce the non-stoichiometric uranium dioxide to stoichiometric uranium dioxide.
GB2514571*A 1970-04-09 1971-04-19 Sintering process Expired GB1320266A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
AUPA085870 1970-04-09
AU25651/71A AU453294B2 (en) 1970-04-09 1971-02-18 Improved sintering process for production of uranium dioxide pellets

Publications (1)

Publication Number Publication Date
GB1320266A true GB1320266A (en) 1973-06-13

Family

ID=25619733

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2514571*A Expired GB1320266A (en) 1970-04-09 1971-04-19 Sintering process

Country Status (3)

Country Link
AU (1) AU453294B2 (en)
CA (1) CA934537A (en)
GB (1) GB1320266A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4389355A (en) * 1981-07-23 1983-06-21 The Babcock & Wilcox Company Sintering UO2 and oxidation of UO2 with microwave radiation
FR2536571A1 (en) * 1982-11-19 1984-05-25 Commissariat Energie Atomique Process for the manufacture of nuclear fuel pellets containing a temporary neutron absorbent.
ES2036493A1 (en) * 1991-04-17 1993-05-16 British Nuclear Fuels Plc Manufacture of sintered uranium dioxide

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4389355A (en) * 1981-07-23 1983-06-21 The Babcock & Wilcox Company Sintering UO2 and oxidation of UO2 with microwave radiation
FR2536571A1 (en) * 1982-11-19 1984-05-25 Commissariat Energie Atomique Process for the manufacture of nuclear fuel pellets containing a temporary neutron absorbent.
ES2036493A1 (en) * 1991-04-17 1993-05-16 British Nuclear Fuels Plc Manufacture of sintered uranium dioxide

Also Published As

Publication number Publication date
AU2565171A (en) 1972-08-24
CA934537A (en) 1973-10-02
AU453294B2 (en) 1974-09-10

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee