SE0202478L - Zirconium Niobium Tin Alloy for Use in Nuclear Reactors and Method of Preparation - Google Patents

Zirconium Niobium Tin Alloy for Use in Nuclear Reactors and Method of Preparation

Info

Publication number
SE0202478L
SE0202478L SE0202478A SE0202478A SE0202478L SE 0202478 L SE0202478 L SE 0202478L SE 0202478 A SE0202478 A SE 0202478A SE 0202478 A SE0202478 A SE 0202478A SE 0202478 L SE0202478 L SE 0202478L
Authority
SE
Sweden
Prior art keywords
preparation
tin alloy
nuclear reactors
zirconium niobium
niobium tin
Prior art date
Application number
SE0202478A
Other languages
Swedish (sv)
Other versions
SE0202478D0 (en
SE526648C2 (en
Inventor
Robert J Comstock
George P Sabol
Original Assignee
Westinghouse Electric Co Llc
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 Westinghouse Electric Co Llc filed Critical Westinghouse Electric Co Llc
Publication of SE0202478D0 publication Critical patent/SE0202478D0/en
Publication of SE0202478L publication Critical patent/SE0202478L/en
Publication of SE526648C2 publication Critical patent/SE526648C2/en

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C16/00Alloys based on zirconium
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22FCHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/16Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
    • C22F1/18High-melting or refractory metals or alloys based thereon
    • C22F1/186High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/07Casings; Jackets characterised by their material, e.g. alloys
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • G21C3/20Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • 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

Abstract

A corrosion resistant zirconium based alloy for use in nuclear fuel cladding is made of a low tin content zirconium alloy consisting essentially of: by weight percent, 0.60-2.0 Nb; when Sn is 0.25, then Fe is 0.50; when Sn is 0.40, then Fe is 0.35 to 0.50; when Sn is 0.50, then Fe is 0.25 to 0.50; when Sn is 0.70, then Fe is 0.05 to 0.50; when Sn is 1.0, then Fe is 0.05 to 0.50 (area 10 of FIG. 1); where the weight percent of Fe plus Sn is greater than 0.75, with no more than 0.50 additional other component elements and with the remainder Zr.
SE0202478A 2000-02-18 2002-08-19 Zirconium Niobium Tin Alloy for Use in Nuclear Reactors and Method of Preparation SE526648C2 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US50691300A 2000-02-18 2000-02-18
PCT/US2001/001845 WO2001061062A1 (en) 2000-02-18 2001-01-19 Zirconium niobium-tin alloy for use in nuclear reactors and method of its manufacture

Publications (3)

Publication Number Publication Date
SE0202478D0 SE0202478D0 (en) 2002-08-19
SE0202478L true SE0202478L (en) 2002-08-19
SE526648C2 SE526648C2 (en) 2005-10-18

Family

ID=24016448

Family Applications (1)

Application Number Title Priority Date Filing Date
SE0202478A SE526648C2 (en) 2000-02-18 2002-08-19 Zirconium Niobium Tin Alloy for Use in Nuclear Reactors and Method of Preparation

Country Status (7)

Country Link
EP (1) EP1259653A1 (en)
JP (1) JP2001262260A (en)
CN (1) CN1152146C (en)
AU (1) AU2001234492A1 (en)
RU (1) RU2002124765A (en)
SE (1) SE526648C2 (en)
WO (1) WO2001061062A1 (en)

Families Citing this family (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100461017B1 (en) 2001-11-02 2004-12-09 한국수력원자력 주식회사 Method for preparing niobium-containing zirconium alloys for nuclear fuel cladding tubes having the excellent corrosion resistance
SE525808C2 (en) 2002-10-30 2005-05-03 Westinghouse Atom Ab Process, use and device for nuclear fuel casing and a fuel cartridge for a nuclear pressurized water reactor
FR2860803B1 (en) 2003-10-08 2006-01-06 Cezus Co Europ Zirconium PROCESS FOR PRODUCING A ZIRCONIUM ALLOY FLAT PRODUCT, FLAT PRODUCT THUS OBTAINED, AND NUCLEAR POWER PLANT REACTOR GRADE REALIZED FROM THE FLAT PRODUCT
US9284629B2 (en) 2004-03-23 2016-03-15 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance due to final heat treatments
US10221475B2 (en) 2004-03-23 2019-03-05 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance
WO2006004499A1 (en) * 2004-07-06 2006-01-12 Westinghouse Electric Sweden Ab Fuel box in a boiling water nuclear reactor
FR2874119B1 (en) 2004-08-04 2006-11-03 Framatome Anp Sas METHOD FOR MANUFACTURING A FUEL SINK TUBE FOR A NUCLEAR REACTOR, AND A TUBE THUS OBTAINED
JP4982654B2 (en) * 2005-03-23 2012-07-25 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Zirconium alloy with improved corrosion resistance and method for producing zirconium alloy with improved corrosion resistance
US7625453B2 (en) 2005-09-07 2009-12-01 Ati Properties, Inc. Zirconium strip material and process for making same
US8116422B2 (en) * 2005-12-29 2012-02-14 General Electric Company LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields
SE530673C2 (en) 2006-08-24 2008-08-05 Westinghouse Electric Sweden Water reactor fuel cladding tube used in pressurized water reactor and boiled water reactor, comprises outer layer of zirconium based alloy which is metallurgically bonded to inner layer of another zirconium based alloy
KR100835830B1 (en) * 2007-01-11 2008-06-05 한국원자력연구원 Preparation method for zirconium alloys for nuclear fuel cladding tubes having excellent corrosion resistance by the control of beta;-nb distribution
SE530783C2 (en) * 2007-01-16 2008-09-09 Westinghouse Electric Sweden Scatter grid for positioning fuel rods
KR100945021B1 (en) 2008-05-09 2010-03-05 한국원자력연구원 Zirconium alloys for nuclear fuel claddings forming the protective oxide, zirconium alloy nuclear fuel claddings prepared by using thereof and method of preparing the same
JP5629446B2 (en) * 2009-09-28 2014-11-19 株式会社東芝 REACTOR CONTROL RODS COMPOSITE, PROCESS FOR PRODUCING THE COMPOSITE AND REACTOR CONTROL RODS USING THE COMPOSITE
EP3064605B1 (en) * 2011-06-16 2021-03-31 Westinghouse Electric Company Llc Method of making a zirconium based cladding tube with improved creep resistance due to final heat treatment
CN104919068A (en) 2013-01-11 2015-09-16 阿海珐核能公司 Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4649023A (en) * 1985-01-22 1987-03-10 Westinghouse Electric Corp. Process for fabricating a zirconium-niobium alloy and articles resulting therefrom
US5112573A (en) * 1989-08-28 1992-05-12 Westinghouse Electric Corp. Zirlo material for light water reactor applications
US5266131A (en) * 1992-03-06 1993-11-30 Westinghouse Electric Corp. Zirlo alloy for reactor component used in high temperature aqueous environment
EP0643144B1 (en) * 1993-03-04 1997-12-29 Vsesojuzny Nauchno-Issledovatelsky Institut Neorga Nicheskikh Materialov Imeni Akademika A.A. Bochvara, Zirconium-based material, article made of the said material for use in the active zones of atomic reactors, and a process for obtaining such articles
JP3564887B2 (en) * 1996-08-09 2004-09-15 三菱マテリアル株式会社 Fuel rod for light water reactor and manufacturing method thereof
US5854818A (en) * 1997-08-28 1998-12-29 Siemens Power Corporation Zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup

Also Published As

Publication number Publication date
CN1152146C (en) 2004-06-02
CN1404532A (en) 2003-03-19
RU2002124765A (en) 2004-03-20
AU2001234492A1 (en) 2001-08-27
EP1259653A1 (en) 2002-11-27
JP2001262260A (en) 2001-09-26
SE0202478D0 (en) 2002-08-19
WO2001061062A1 (en) 2001-08-23
SE526648C2 (en) 2005-10-18

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Legal Events

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NUG Patent has lapsed