[go: up one dir, main page]

FR2307884A1 - Thermo mechanical treatment of zirconium ALLOYS - for nuclear reactors by annealing and subjecting to tensile creep deformation - Google Patents

Thermo mechanical treatment of zirconium ALLOYS - for nuclear reactors by annealing and subjecting to tensile creep deformation

Info

Publication number
FR2307884A1
FR2307884A1 FR7511688A FR7511688A FR2307884A1 FR 2307884 A1 FR2307884 A1 FR 2307884A1 FR 7511688 A FR7511688 A FR 7511688A FR 7511688 A FR7511688 A FR 7511688A FR 2307884 A1 FR2307884 A1 FR 2307884A1
Authority
FR
France
Prior art keywords
alloy
subjecting
tensile creep
nuclear reactors
annealing
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.)
Granted
Application number
FR7511688A
Other languages
French (fr)
Other versions
FR2307884B1 (en
Inventor
Ira S Levy
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.)
Framatome ANP Richland Inc
Original Assignee
Exxon Nuclear Co Inc
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 Exxon Nuclear Co Inc filed Critical Exxon Nuclear Co Inc
Priority to FR7511688A priority Critical patent/FR2307884A1/en
Publication of FR2307884A1 publication Critical patent/FR2307884A1/en
Application granted granted Critical
Publication of FR2307884B1 publication Critical patent/FR2307884B1/fr
Granted legal-status Critical Current

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

Landscapes

  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Heat Treatment Of Nonferrous Metals Or Alloys (AREA)

Abstract

An alloy comprising >=95% Zr and at least one of Cr, Sn Nb, Fe, Ta, Ni and Al which is thoroughly annealed is treated by subjecting the alloy to a tensile creep strain of 3-10% while holding in a temp. range at which creep will occur yet which is below the temp. for significant recovery by loading at a strain rate of 0.001-0.01 inch/inch/minute until the tensile creep strain is obtd. and holding at the final load for at least 15 mins. The treated alloy has high strength, ductility and corrosion resistance to steam. Tubes of the alloy are heated on the upper part of the alpha-range for Zr to anneal and then treated as described. Treated tubes of the alloy are used in nuclear reactors.
FR7511688A 1975-04-15 1975-04-15 Thermo mechanical treatment of zirconium ALLOYS - for nuclear reactors by annealing and subjecting to tensile creep deformation Granted FR2307884A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7511688A FR2307884A1 (en) 1975-04-15 1975-04-15 Thermo mechanical treatment of zirconium ALLOYS - for nuclear reactors by annealing and subjecting to tensile creep deformation

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7511688A FR2307884A1 (en) 1975-04-15 1975-04-15 Thermo mechanical treatment of zirconium ALLOYS - for nuclear reactors by annealing and subjecting to tensile creep deformation

Publications (2)

Publication Number Publication Date
FR2307884A1 true FR2307884A1 (en) 1976-11-12
FR2307884B1 FR2307884B1 (en) 1978-06-30

Family

ID=9153942

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7511688A Granted FR2307884A1 (en) 1975-04-15 1975-04-15 Thermo mechanical treatment of zirconium ALLOYS - for nuclear reactors by annealing and subjecting to tensile creep deformation

Country Status (1)

Country Link
FR (1) FR2307884A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0246986A1 (en) * 1986-05-21 1987-11-25 CEZUS Compagnie Européenne du Zirconium Process for manufacturing strips from partially recrystallized zircaloy 2 or zircaloy 4, and strips obtained in this way

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
NEANT *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0246986A1 (en) * 1986-05-21 1987-11-25 CEZUS Compagnie Européenne du Zirconium Process for manufacturing strips from partially recrystallized zircaloy 2 or zircaloy 4, and strips obtained in this way
FR2599049A1 (en) * 1986-05-21 1987-11-27 Cezus Co Europ Zirconium PROCESS FOR MANUFACTURING A PARTIALLY RECRYSTALLIZED ZIRCALOY 2 OR ZIRCALOY 4 STRIP AND STRIP OBTAINED
US4775428A (en) * 1986-05-21 1988-10-04 Compagnie Europeenne Du Zirconium Cezus Production of a strip of zircaloy 2 or zircaloy 4 in partially recrystallized state

Also Published As

Publication number Publication date
FR2307884B1 (en) 1978-06-30

Similar Documents

Publication Publication Date Title
US3963534A (en) Zirconium alloys
ES432572A1 (en) Annealing of NiTi martensitic memory alloys and product produced thereby
US3347715A (en) Heat treatment of steel
GB2200925A (en) Radiation resistant austenitic stainless steel alloys
US3563728A (en) Austenitic stainless steels for use in nuclear reactors
Cupp The effect of neutron irradiation on the mechanical properties of zirconium-2.5% niobium alloy
US3341373A (en) Method of treating zirconium-base alloys
GB1261852A (en) Production of metal resistant to neutron irradiation
FR2307884A1 (en) Thermo mechanical treatment of zirconium ALLOYS - for nuclear reactors by annealing and subjecting to tensile creep deformation
GB932336A (en) Process for treating zirconium alloys
KR940010230B1 (en) Improvement in structural parts of austenitic nichel-chromium-iron alloy
US3669759A (en) Thermomechanical treatment for improving ductility of carbide-stabilized austenite stainless steel
EP0062128B1 (en) Method of improving post-irradiation ductility of precipitation hardenable alloys
GB952207A (en) Improvements in or relating to transmission chains and method for the production thereof
ES453423A1 (en) Heat treatment of zirconium base alloy and product obtained thereby
US2924518A (en) Zirconium alloys
JP2687538B2 (en) Zr alloy for nuclear reactor fuel assemblies
US4435231A (en) Cold worked ferritic alloys and components
GB1051835A (en) Heat treatment of refractory metals
JP2521665B2 (en) Nuclear plant spring
US3431104A (en) Zirconium base alloy
GB1484222A (en) Thermo-mechanical treatment of zirconium alloys
BLOOM et al. Postirradiation mechanical properties of types 304 plus 0. 15 percent Ti stainless steel(Mechanical properties of types 304 and 304 plus 0. 15 percent Ti stainless steel after irradiation at temperatures in range of 400 to 820 C)
Gray Recovery and recrystallization of zirconium and its alloys. Part 2. Annealing of cold-worked zirconium
JPS6321590A (en) Fuel aggregate

Legal Events

Date Code Title Description
ST Notification of lapse