IN2014DN03008A - - Google Patents

Info

Publication number
IN2014DN03008A
IN2014DN03008A IN3008DEN2014A IN2014DN03008A IN 2014DN03008 A IN2014DN03008 A IN 2014DN03008A IN 3008DEN2014 A IN3008DEN2014 A IN 3008DEN2014A IN 2014DN03008 A IN2014DN03008 A IN 2014DN03008A
Authority
IN
India
Prior art keywords
core
phase
aluminium
ual
nuclear fuel
Prior art date
Application number
Inventor
Bertrand Stepnik
Michel Grasse
Gilles Bourdat
Christel Coullomb
Christophe Moyroud
Original Assignee
Cie Pour Letude Et La Realisation De Combustibles Atomiques
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 Cie Pour Letude Et La Realisation De Combustibles Atomiques filed Critical Cie Pour Letude Et La Realisation De Combustibles Atomiques
Publication of IN2014DN03008A publication Critical patent/IN2014DN03008A/en

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • 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
    • G21C3/60—Metallic fuel; Intermetallic dispersions
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B22—CASTING; POWDER METALLURGY
    • B22F—WORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F3/00—Manufacture of workpieces or articles from metallic powder characterised by the manner of compacting or sintering; Apparatus specially adapted therefor ; Presses and furnaces
    • B22F3/10—Sintering only
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B22—CASTING; POWDER METALLURGY
    • B22F—WORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F5/00—Manufacture of workpieces or articles from metallic powder characterised by the special shape of the product
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B22—CASTING; POWDER METALLURGY
    • B22F—WORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F9/00—Making metallic powder or suspensions thereof
    • B22F9/02—Making metallic powder or suspensions thereof using physical processes
    • B22F9/04—Making metallic powder or suspensions thereof using physical processes starting from solid material, e.g. by crushing, grinding or milling
    • 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
    • G21C3/02—Fuel elements
    • 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
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G4/00—Radioactive sources
    • G21G4/04—Radioactive sources other than neutron sources
    • G21G4/06—Radioactive sources other than neutron sources characterised by constructional features
    • G21G4/08—Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical application
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T29/00—Metal working
    • Y10T29/49—Method of mechanical manufacture
    • Y10T29/49826—Assembling or joining
    • Y10T29/49828—Progressively advancing of work assembly station or assembled portion of work

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • Manufacturing & Machinery (AREA)
  • Mechanical Engineering (AREA)
  • Dispersion Chemistry (AREA)
  • Chemical & Material Sciences (AREA)
  • Metallurgy (AREA)
  • Powder Metallurgy (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Gasket Seals (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Application Of Or Painting With Fluid Materials (AREA)

Abstract

A METHOD OF PRODUCING A NUCLEAR FUEL PRODUCT (1) THE METHOD COMPRISING THE STEPS OF: PROVIDING A CORE (3) COMPRISING ALUMINIUM AND LOW ENRICHED URANIUM; AND SEALING SAID CORE IN A CLADDING (5); WHEREIN SAID CORE (3) HAS A LOW ENRICHED URANIUM LOADING STRICTLY HIGHER THAN 3.0 G U/CM AND COMPRISES LESS THAN 10 WT% OF ALUMINIUM PHASE AND/OR ALUMINIUM COMPOUNDS OTHER THAN UALPHASE THAN UAL PHASE AND THAN UAL PHASE. CORRESPONDING NUCLEAR FUEL PRODUCT (1).
IN3008DEN2014 2011-10-21 2011-10-21 IN2014DN03008A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/IB2011/002957 WO2013057533A1 (en) 2011-10-21 2011-10-21 Method for producing nuclear fuel products with a high loading of low enriched uranium and corresponding nuclear kernbrennstoff

Publications (1)

Publication Number Publication Date
IN2014DN03008A true IN2014DN03008A (en) 2015-05-08

Family

ID=45507717

Family Applications (1)

Application Number Title Priority Date Filing Date
IN3008DEN2014 IN2014DN03008A (en) 2011-10-21 2011-10-21

Country Status (10)

Country Link
US (2) US9972408B2 (en)
EP (1) EP2769383B1 (en)
KR (1) KR101800265B1 (en)
CN (1) CN104054134B (en)
AR (1) AR088394A1 (en)
AU (1) AU2011379288B2 (en)
HU (1) HUE039002T2 (en)
IN (1) IN2014DN03008A (en)
PL (1) PL2769383T3 (en)
WO (1) WO2013057533A1 (en)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101539345B1 (en) * 2014-02-06 2015-07-27 한국원자력연구원 The preparing method of tubular nuclear fuel rod and the tubular nuclear fuel rod thereby
CN104694974B (en) * 2015-02-13 2017-07-07 中国科学院高能物理研究所 U-Al alloy and its fused salt electrolysis preparation method thereof
CN108213418A (en) * 2017-12-21 2018-06-29 中核北方核燃料元件有限公司 A kind of U-Al alloy target piece core base preparation method
KR102229519B1 (en) * 2019-05-22 2021-03-18 한국원자력연구원 METHOD FOR MANUFACTURING URANIUM TARGET TO BE SOLUBLE IN BASIC SOLUTION AND METHOD FOR EXTRACTING RADIOACTIVE Mo-99 USING THE SAME
CN113000839A (en) * 2019-12-20 2021-06-22 中核北方核燃料元件有限公司 Method for 3D printing of key parts of fuel elements of 6061 aluminum alloy test reactor
EP3929941A1 (en) * 2020-06-26 2021-12-29 Sck Cen Nuclear fuel for isotope extraction
FR3125164B1 (en) * 2021-07-06 2024-02-16 Framatome Sa Process for manufacturing a nuclear fuel element and nuclear fuel element
EP4170681A1 (en) * 2021-10-19 2023-04-26 Framatome Plate-shaped nuclear fuel element and method of manufacturing the same
CN114267460B (en) * 2021-12-22 2023-03-24 西安交通大学 Plate-shaped fuel element for suppressing foaming phenomenon

Family Cites Families (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2917383A (en) * 1949-07-29 1959-12-15 Henry A Saller Fabrication of uranium-aluminum alloys
BE570983A (en) 1957-09-10
US3213032A (en) * 1964-11-13 1965-10-19 Joseph P Hammond Process for sintering uranium nitride with a sintering aid depressant
US3318670A (en) * 1966-08-12 1967-05-09 Earl S Grimmett Production of actinide aluminide in a fluidized bed
CA987135A (en) * 1973-06-28 1976-04-13 Alan M. Ross Uranium-base alloys
DE3042424A1 (en) * 1980-11-11 1982-06-16 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe PLATE-SHAPED HIGH-PERFORMANCE FUEL FUEL ELEMENT WITH LOW-ENRICHED URANIUM AND METHOD FOR THE PRODUCTION THEREOF
GB2282478B (en) 1993-10-01 1997-08-13 Us Energy Method of fabricating 99Mo production targets using low enriched uranium
US5978432A (en) * 1998-04-17 1999-11-02 Korea Atomic Energy Research Institute Dispersion fuel with spherical uranium alloy, and the fuel fabrication process
EP1345239B1 (en) * 2002-03-11 2008-06-04 Urenco Nederland B.V. Nuclear fuel comprising a uranium-molybdenum alloy
KR100643792B1 (en) * 2005-02-16 2006-11-10 한국원자력연구소 Multi-core Fuel Rod for Research Reactor and Manufacturing Method Thereof
CA2710432C (en) * 2007-12-26 2016-04-26 Thorium Power, Inc. Nuclear reactor, fuel assembly consisting of driver-breeding modules for a nuclear reactor and a fuel cell for a fuel assembly
JP5612852B2 (en) 2009-12-24 2014-10-22 株式会社グローバル・ニュークリア・フュエル・ジャパン Fuel assemblies for boiling water reactors and cores of boiling water reactors
CN102212718B (en) * 2011-06-14 2013-01-16 苏州热工研究院有限公司 Low tin-zirconium alloy material for nuclear reactor fuel assembly

Also Published As

Publication number Publication date
AU2011379288A1 (en) 2014-05-15
HUE039002T2 (en) 2018-12-28
KR101800265B1 (en) 2017-11-22
EP2769383A1 (en) 2014-08-27
EP2769383B1 (en) 2018-04-18
US10847275B2 (en) 2020-11-24
PL2769383T3 (en) 2018-10-31
AU2011379288B2 (en) 2015-09-10
US20150340110A1 (en) 2015-11-26
WO2013057533A1 (en) 2013-04-25
CN104054134B (en) 2016-09-07
CN104054134A (en) 2014-09-17
AR088394A1 (en) 2014-05-28
US9972408B2 (en) 2018-05-15
US20180261346A1 (en) 2018-09-13
KR20140079497A (en) 2014-06-26
RU2014120425A (en) 2015-11-27

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