FR2538940B1 - Procede de realisation d'une gaine en alliage de zirconium pour le combustible d'un element combustible de reacteur nucleaire - Google Patents

Procede de realisation d'une gaine en alliage de zirconium pour le combustible d'un element combustible de reacteur nucleaire

Info

Publication number
FR2538940B1
FR2538940B1 FR8320969A FR8320969A FR2538940B1 FR 2538940 B1 FR2538940 B1 FR 2538940B1 FR 8320969 A FR8320969 A FR 8320969A FR 8320969 A FR8320969 A FR 8320969A FR 2538940 B1 FR2538940 B1 FR 2538940B1
Authority
FR
France
Prior art keywords
fuel
producing
nuclear reactor
zirconium alloy
alloy sheath
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
FR8320969A
Other languages
English (en)
Other versions
FR2538940A1 (fr
Inventor
Eckard Steinberg
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.)
Kraftwerk Union AG
Original Assignee
Kraftwerk Union AG
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 Kraftwerk Union AG filed Critical Kraftwerk Union AG
Publication of FR2538940A1 publication Critical patent/FR2538940A1/fr
Application granted granted Critical
Publication of FR2538940B1 publication Critical patent/FR2538940B1/fr
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • 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
    • 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
    • Y10TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10STECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90Particular material or material shapes for fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Materials Engineering (AREA)
  • Thermal Sciences (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat Treatment Of Articles (AREA)
  • Heat Treatment Of Nonferrous Metals Or Alloys (AREA)
FR8320969A 1982-12-30 1983-12-28 Procede de realisation d'une gaine en alliage de zirconium pour le combustible d'un element combustible de reacteur nucleaire Expired FR2538940B1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19823248686 DE3248686A1 (de) 1982-12-30 1982-12-30 Verfahren zum herstellen eines huellrohres aus einer zirkoniumlegierung fuer kernreaktorbrennstoff eines kernreaktorbrennelementes

Publications (2)

Publication Number Publication Date
FR2538940A1 FR2538940A1 (fr) 1984-07-06
FR2538940B1 true FR2538940B1 (fr) 1988-12-09

Family

ID=6182194

Family Applications (1)

Application Number Title Priority Date Filing Date
FR8320969A Expired FR2538940B1 (fr) 1982-12-30 1983-12-28 Procede de realisation d'une gaine en alliage de zirconium pour le combustible d'un element combustible de reacteur nucleaire

Country Status (6)

Country Link
US (1) US4512819A (fr)
JP (1) JPS59126764A (fr)
BE (1) BE898584A (fr)
BR (1) BR8307168A (fr)
DE (1) DE3248686A1 (fr)
FR (1) FR2538940B1 (fr)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3528545A1 (de) * 1985-08-08 1987-02-19 Kraftwerk Union Ag Brennstab fuer ein kernreaktorbrennelement
US5188676A (en) * 1991-08-23 1993-02-23 General Electric Company Method for annealing zircaloy to improve nodular corrosion resistance
TW250567B (fr) * 1993-05-13 1995-07-01 Gen Electric
US7194980B2 (en) * 2003-07-09 2007-03-27 John Stuart Greeson Automated carrier-based pest control system
US9139895B2 (en) * 2004-09-08 2015-09-22 Global Nuclear Fuel—Americas, LLC Zirconium alloy fuel cladding for operation in aggressive water chemistry
US8043448B2 (en) * 2004-09-08 2011-10-25 Global Nuclear Fuel-Americas, Llc Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3294594A (en) * 1963-11-08 1966-12-27 Nat Distillers Chem Corp Method of imparting corrosion resistance to zirconium base alloys
GB1089610A (en) * 1965-10-07 1967-11-01 Westinghouse Electric Corp Method for treating surfaces of zirconium alloy members
DE1801997A1 (de) * 1967-10-30 1969-06-26 Westinghouse Electric Corp Verfahren zur Oberflaechenbehandlung von Kernreaktorbauteilen aus Zirkonlegierungen
US3689324A (en) * 1968-09-27 1972-09-05 George W Wiener Process for obtaining preferred orientation in zirconium and its alloy
US3826124A (en) * 1972-10-25 1974-07-30 Zirconium Technology Corp Manufacture of tubes with improved metallic yield strength and elongation properties
FR2219978B1 (fr) * 1973-03-02 1976-04-30 Commissariat Energie Atomique
US3847684A (en) * 1973-09-20 1974-11-12 Teledyne Wah Chang Method of quenching zirconium and alloys thereof
JPS51101077A (fr) * 1975-03-04 1976-09-07 Konishiroku Photo Ind
FR2334763A1 (fr) * 1975-12-12 1977-07-08 Ugine Aciers Procede permettant d'ameliorer la tenue a chaud du zirconium et de ses alliages
CA1139023A (fr) * 1979-06-04 1983-01-04 John H. Davies Traitement mecanothermique pour blindage composite de charge nucleaire

Also Published As

Publication number Publication date
DE3248686A1 (de) 1984-07-12
FR2538940A1 (fr) 1984-07-06
US4512819A (en) 1985-04-23
JPS59126764A (ja) 1984-07-21
JPS6123265B2 (fr) 1986-06-05
BR8307168A (pt) 1984-08-07
BE898584A (fr) 1984-04-16

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Legal Events

Date Code Title Description
TP Transmission of property
ST Notification of lapse