SE8104214L - SET TO MANUFACTURE Capsules of Zirconium-Based Alloy COMBUSTION RODS FOR NUCLEAR REACTORS - Google Patents

SET TO MANUFACTURE Capsules of Zirconium-Based Alloy COMBUSTION RODS FOR NUCLEAR REACTORS

Info

Publication number
SE8104214L
SE8104214L SE8104214A SE8104214A SE8104214L SE 8104214 L SE8104214 L SE 8104214L SE 8104214 A SE8104214 A SE 8104214A SE 8104214 A SE8104214 A SE 8104214A SE 8104214 L SE8104214 L SE 8104214L
Authority
SE
Sweden
Prior art keywords
temperature
zirconium
annealing
final
extruded
Prior art date
Application number
SE8104214A
Other languages
Swedish (sv)
Other versions
SE426891B (en
Inventor
G Vesterlund
Original Assignee
Asea Atom Ab
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 Asea Atom Ab filed Critical Asea Atom Ab
Priority to SE8104214A priority Critical patent/SE426891B/en
Priority to DE19823224685 priority patent/DE3224685A1/en
Priority to FR8211723A priority patent/FR2509510B1/en
Priority to FI822395A priority patent/FI72007C/en
Priority to JP57116327A priority patent/JPS5825466A/en
Priority to BE0/208548A priority patent/BE893788A/en
Publication of SE8104214L publication Critical patent/SE8104214L/en
Publication of SE426891B publication Critical patent/SE426891B/en

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/16—Changing 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
    • C22F1/18—High-melting or refractory metals or alloys based thereon
    • C22F1/186—High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
    • 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
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Thermal Sciences (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Powder Metallurgy (AREA)
  • Heat Treatment Of Steel (AREA)
  • Heat Treatment Of Nonferrous Metals Or Alloys (AREA)
  • Extrusion Of Metal (AREA)

Abstract

In a process for producing encapsulation tubes for nuclear reactor fuel rods, a zirconium-base alloy is extruded at a temperature below 680 DEG C and the extruded material (product) is cold-rolled. Between the individual cold rollings, intermediate annealings are carried out, at least one of which takes place at a temperature which exceeds 650 DEG C in the alpha -phase range. The final cold rolling is followed by a final annealing. According to the invention, the extruded product is cooled after every intermediate annealing exceeding 650 DEG C at a rate which is at least 5 DEG C/minute in the temperature range from the annealing temperature down to 650 DEG C before it is subjected to the next cold rolling. Annealings which take place after the final intermediate annealing at a temperature above 600 DEG C in the alpha -phase range are carried out at a temperature of not more than 600 DEG C. The encapsulation tubes produced in accordance with the invention have not only a high corrosion resistance but also good mechanical properties.
SE8104214A 1981-07-07 1981-07-07 SET TO MANUFACTURE Capsules of Zirconium-Based Alloy COMBUSTION RODS FOR NUCLEAR REACTORS SE426891B (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
SE8104214A SE426891B (en) 1981-07-07 1981-07-07 SET TO MANUFACTURE Capsules of Zirconium-Based Alloy COMBUSTION RODS FOR NUCLEAR REACTORS
DE19823224685 DE3224685A1 (en) 1981-07-07 1982-07-02 Process for producing encapsulation tubes composed of zirconium-base alloy for nuclear reactor fuel rods
FR8211723A FR2509510B1 (en) 1981-07-07 1982-07-05 METHOD FOR MANUFACTURING COATING TUBES IN A ZIRCONIUM-BASED ALLOY FOR FUEL BARS FOR NUCLEAR REACTORS
FI822395A FI72007C (en) 1981-07-07 1982-07-06 SAETT ATT TILLVERKA KAPSELROER AV ZIRKONIUMBASERAD LEGERING FOER BRAENSLESTAVAR TILL KAERNREAKTORER.
JP57116327A JPS5825466A (en) 1981-07-07 1982-07-06 Manufacture of zirconium base alloy-clad pipe
BE0/208548A BE893788A (en) 1981-07-07 1982-07-07 PROCESS FOR THE MANUFACTURE OF ZIRCONIUM-BASED ALLOY SHEATHING TUBES AND TUBES OBTAINED THEREBY

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SE8104214A SE426891B (en) 1981-07-07 1981-07-07 SET TO MANUFACTURE Capsules of Zirconium-Based Alloy COMBUSTION RODS FOR NUCLEAR REACTORS

Publications (2)

Publication Number Publication Date
SE8104214L true SE8104214L (en) 1983-01-08
SE426891B SE426891B (en) 1983-02-14

Family

ID=20344213

Family Applications (1)

Application Number Title Priority Date Filing Date
SE8104214A SE426891B (en) 1981-07-07 1981-07-07 SET TO MANUFACTURE Capsules of Zirconium-Based Alloy COMBUSTION RODS FOR NUCLEAR REACTORS

Country Status (6)

Country Link
JP (1) JPS5825466A (en)
BE (1) BE893788A (en)
DE (1) DE3224685A1 (en)
FI (1) FI72007C (en)
FR (1) FR2509510B1 (en)
SE (1) SE426891B (en)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0196286B1 (en) * 1985-03-12 1989-05-17 Santrade Ltd. Method of manufacturing tubes of zirconium alloys with improved corrosion resistance for thermal nuclear reactors
FR2579122B1 (en) * 1985-03-19 1989-06-30 Cezus Co Europ Zirconium PROCESS FOR PRODUCING COMPOSITE SHEATH TUBES FOR NUCLEAR FUEL AND PRODUCTS OBTAINED
US4671826A (en) * 1985-08-02 1987-06-09 Westinghouse Electric Corp. Method of processing tubing
US4717428A (en) * 1985-08-02 1988-01-05 Westinghouse Electric Corp. Annealing of zirconium based articles by induction heating
DE3528545A1 (en) * 1985-08-08 1987-02-19 Kraftwerk Union Ag FUEL ROD FOR A CORE REACTOR FUEL
SE464267B (en) * 1985-10-22 1991-03-25 Westinghouse Electric Corp STIRCULATE NUCLEAR BURNT CAPSEL
FR2599049B1 (en) * 1986-05-21 1988-07-01 Cezus Co Europ Zirconium PROCESS FOR THE MANUFACTURE OF A ZIRCALOY 2 OR ZIRCALOY 4 SHEET PARTIALLY RECRYSTALLIZED AND SHEET OBTAINED
US5245645A (en) * 1991-02-04 1993-09-14 Siemens Aktiengesellschaft Structural part for a nuclear reactor fuel assembly and method for producing this structural part
ES2084847T3 (en) * 1991-02-04 1996-05-16 Siemens Ag STRUCTURAL PART FOR A NUCLEAR REACTOR FUEL ELEMENT, AND PROCEDURE FOR OBTAINING THIS STRUCTURAL PART.
DE19709929C1 (en) 1997-03-11 1998-08-13 Siemens Ag Cladding tube of a fuel rod for a boiling water reactor fuel element and method for its production

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3431104A (en) * 1966-08-08 1969-03-04 Atomic Energy Commission Zirconium base alloy
CA988748A (en) * 1973-05-11 1976-05-11 Donald J. Cameron High strenght corrosion-resistant zirconium aluminum alloys
FR2334763A1 (en) * 1975-12-12 1977-07-08 Ugine Aciers PROCESS FOR IMPROVING THE HOT RESISTANCE OF ZIRCONIUM AND ITS ALLOYS
CA1139023A (en) * 1979-06-04 1983-01-04 John H. Davies Thermal-mechanical treatment of composite nuclear fuel element cladding

Also Published As

Publication number Publication date
FR2509510A1 (en) 1983-01-14
FI72007B (en) 1986-11-28
DE3224685A1 (en) 1983-01-20
BE893788A (en) 1982-11-03
FR2509510B1 (en) 1988-06-17
SE426891B (en) 1983-02-14
JPS5825466A (en) 1983-02-15
FI822395L (en) 1983-01-08
FI822395A0 (en) 1982-07-06
FI72007C (en) 1987-03-09

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