SE8204071L - SET TO MANUFACTURE Capsules of Zirconium-Based Alloy for Fuel Rods for Nuclear Reactors - Google Patents

SET TO MANUFACTURE Capsules of Zirconium-Based Alloy for Fuel Rods for Nuclear Reactors

Info

Publication number
SE8204071L
SE8204071L SE8204071A SE8204071A SE8204071L SE 8204071 L SE8204071 L SE 8204071L SE 8204071 A SE8204071 A SE 8204071A SE 8204071 A SE8204071 A SE 8204071A SE 8204071 L SE8204071 L SE 8204071L
Authority
SE
Sweden
Prior art keywords
zirconium
based alloy
cold
fuel rods
nuclear reactors
Prior art date
Application number
SE8204071A
Other languages
Swedish (sv)
Other versions
SE431562B (en
SE8204071D0 (en
Inventor
G Vesterlund
E T Andersson
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 SE8204071A priority Critical patent/SE431562B/en
Publication of SE8204071D0 publication Critical patent/SE8204071D0/en
Publication of SE8204071L publication Critical patent/SE8204071L/en
Publication of SE431562B publication Critical patent/SE431562B/en

Links

Classifications

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

Abstract

The invention relates to a process for making cladding pipes from a zirconium-based alloy for fuel rods used in nuclear reactors. In the process according to the invention, the zirconium-based alloy is extruded, and the extruded product is rolled in the cold state. The process also involves some annealing steps, intermediate annealing steps, intermediate cold rolling steps and a β-quenching step before the last cold-rolling stage. The cladding pipes thus obtained have both good corrosion properties and good mechanical properties due to the fact that β-quenching is carried out before a cold- rolling operation. The intermediate annealing is then conducted at a temperature which is higher than 610 degrees C, and is up to 675 degrees C.
SE8204071A 1982-07-01 1982-07-01 Process for making cladding pipes from a zirconium-based alloy for fuel rods used in nuclear reactors SE431562B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
SE8204071A SE431562B (en) 1982-07-01 1982-07-01 Process for making cladding pipes from a zirconium-based alloy for fuel rods used in nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SE8204071A SE431562B (en) 1982-07-01 1982-07-01 Process for making cladding pipes from a zirconium-based alloy for fuel rods used in nuclear reactors

Publications (3)

Publication Number Publication Date
SE8204071D0 SE8204071D0 (en) 1982-07-01
SE8204071L true SE8204071L (en) 1984-01-02
SE431562B SE431562B (en) 1984-02-13

Family

ID=20347254

Family Applications (1)

Application Number Title Priority Date Filing Date
SE8204071A SE431562B (en) 1982-07-01 1982-07-01 Process for making cladding pipes from a zirconium-based alloy for fuel rods used in nuclear reactors

Country Status (1)

Country Link
SE (1) SE431562B (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4671826A (en) * 1985-08-02 1987-06-09 Westinghouse Electric Corp. Method of processing tubing

Also Published As

Publication number Publication date
SE431562B (en) 1984-02-13
SE8204071D0 (en) 1982-07-01

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