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AU6064900A - Drying nuclear fuel materials - Google Patents

Drying nuclear fuel materials

Info

Publication number
AU6064900A
AU6064900A AU60649/00A AU6064900A AU6064900A AU 6064900 A AU6064900 A AU 6064900A AU 60649/00 A AU60649/00 A AU 60649/00A AU 6064900 A AU6064900 A AU 6064900A AU 6064900 A AU6064900 A AU 6064900A
Authority
AU
Australia
Prior art keywords
nuclear fuel
fuel materials
drying
drying nuclear
materials
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.)
Abandoned
Application number
AU60649/00A
Inventor
Albert E Abel
Clyde Frank
Robert W Mouk
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.)
Commodore Applied Technologies Inc
Original Assignee
Commodore Applied Technologies Inc
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 Commodore Applied Technologies Inc filed Critical Commodore Applied Technologies Inc
Publication of AU6064900A publication Critical patent/AU6064900A/en
Abandoned legal-status Critical Current

Links

Classifications

    • F26B21/35—
    • F26B21/40—
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07—Leak testing
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Treatment Of Sludge (AREA)
AU60649/00A 1999-07-01 2000-06-29 Drying nuclear fuel materials Abandoned AU6064900A (en)

Applications Claiming Priority (5)

Application Number Priority Date Filing Date Title
US14198299P 1999-07-01 1999-07-01
US60141982 1999-07-01
US60596400A 2000-06-28 2000-06-28
US09605964 2000-06-28
PCT/US2000/018214 WO2001003144A2 (en) 1999-07-01 2000-06-29 Drying nuclear fuel materials

Publications (1)

Publication Number Publication Date
AU6064900A true AU6064900A (en) 2001-01-22

Family

ID=26839634

Family Applications (1)

Application Number Title Priority Date Filing Date
AU60649/00A Abandoned AU6064900A (en) 1999-07-01 2000-06-29 Drying nuclear fuel materials

Country Status (2)

Country Link
AU (1) AU6064900A (en)
WO (1) WO2001003144A2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106482451B (en) * 2016-09-23 2022-05-27 广东核电合营有限公司 Vacuum drying and helium filling device for spent fuel storage and transportation container

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1960289C3 (en) * 1969-12-02 1975-09-11 Kernforschungsanlage Juelich Gmbh, 5170 Juelich Process for the production of spherical fuel and / or breeding material particles from uranium dioxide for fuel and / or breeding elements for nuclear reactors and breeding reactors
DE2222527A1 (en) * 1972-05-08 1973-11-22 Rbg Reaktor Brennelemente Gmbh Uranium dioxide prodn - by the ammonium-uranyl carbonate method
US3980757A (en) * 1972-11-06 1976-09-14 The Babcock & Wilcox Company Process for uranium separation and preparation of UO4.2NH3.2HF
US3923959A (en) * 1973-11-28 1975-12-02 Us Energy Method for preparing actinide nitrides
JPS5278800A (en) * 1975-12-26 1977-07-02 Japan Atom Energy Res Inst Drying of ammonia gas flow
US4696769A (en) * 1983-07-27 1987-09-29 General Electric Company Method and binder for the manufacture of nuclear fuel pellets, and the product
JPH0653572B2 (en) * 1986-05-27 1994-07-20 三菱マテリアル株式会社 Method for producing uranium dioxide from uranium hexafluoride

Also Published As

Publication number Publication date
WO2001003144A3 (en) 2001-09-07
WO2001003144A2 (en) 2001-01-11

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Legal Events

Date Code Title Description
MK6 Application lapsed section 142(2)(f)/reg. 8.3(3) - pct applic. not entering national phase