US3865635A - Method of making tubes and similar products of a zirconium alloy - Google Patents

Method of making tubes and similar products of a zirconium alloy Download PDF

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US3865635A
US3865635A US393816A US39381673A US3865635A US 3865635 A US3865635 A US 3865635A US 393816 A US393816 A US 393816A US 39381673 A US39381673 A US 39381673A US 3865635 A US3865635 A US 3865635A
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cold working
temperature
range
working step
percent
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Ake Sixten Boris Hofvenstam
Erik Thomas Andersson
Olof Krister Kallstrom
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Santrade Ltd
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Sandvik AB
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Assigned to SANTRADE LTD., A CORP. OF SWITZERLAND reassignment SANTRADE LTD., A CORP. OF SWITZERLAND ASSIGNMENT OF ASSIGNORS INTEREST. Assignors: SANDVIK AKTIEBOLAG, A CORP. OF SWEDEN
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    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors

Definitions

  • ABSTRACT Stallard Attorney, Agent, or Firm-Pierce, Scheffler & Parker
  • the present invention relates to a method of making tubes, and other products, of zirconium alloys containing (in percent by weight) 1.2 l.7 Sn, 0.07 0.24 Fe, 0.05 0. [5 Cr, 0 0.08 Ni, 0.09 O.l6 0, balance zirconium and customary impurities, the same being known as the Zircaloys or specifically Zircaloy 2" and Zircaloy 4.
  • oz-range is meant the lower temperature interval wherein the close-packed hexagonal crystal lattice is stable, while the Ii-range means the higher temperature interval wherein the body-centered cubic crystal lattice is stable.
  • the boundary between the aand B-ranges is at 862 C., while in all alloys there is a two-phase a B range at around this temperature.
  • zirconium-niobium alloys containing 1-5 percent Nb and up to 3 percent Sn. These alloys are specifically designed for high strength.
  • the basic strengthening mechanism is a finely dispersed precipitation obtained through a quenchage treatment the alloys being characterized as age-hardenable.
  • the production of these alloys includes as the last steps a heat treatment in the B- or a B-range followed by quenching in water to a martensitic structure, possible cold work for example by rolling or drawing, and aging or tempering in the a-range at around 500 C.
  • zirzonium-niobium alloys A major concern for the zirzonium-niobium alloys is their corrosion resistance in the nuclear reactor environment. This can be improved by proper selection of temperature and time in the quench-age treatment, as is known for example from a number of patent publications, in which the procedure for reaching optimum strength and corrosion properties is clarified.
  • the active constituent in the zirconium-niobium alloys is a secondary phase called Li-niobium.” It consists essentially ofniobium, thus requiring a high degree of segregation of niobium between the a-zirconium and B-niobiuin phases. The strong segregation provides for finely dispersed precipitation and resistance to coarsening, which is a basic prerequisite for an agehardenable alloy. In contrast to this, most other zirconium alloys, and specifically Zircaloy, have a secondary phase consisting essentially of zirconium and requiring a moderate segregation of the alloying elements tin, iron, chromium.
  • the solubility in the a-phase of the Zircaloy" alloying elements is great compared to that of niobium. This makes the precipitation hardening in Zircaloy weak, and the alloy has never been regarded as age-hardenable.
  • the conventional way of controlling the mechanical properties of Zircaloy" tubing involves choosing the degree of cold work in the final rolling step and the temperature of the final annealing to give optimum conditions. This gives awOrk-hardened and a more or less recovered and recrystallized structure.
  • the canning tubes are required to possess both strength and ductility.
  • the creep strength can be improved by adjusting the degree of cold work and the final annealing temperature, but with a sacrifice in production economy.
  • the method according to the invention has not caused any depreciation of the corrosion properties, which depreciation might have been expected in view of the earlier-mentioned influence of the secondary phase particles.
  • the normal way of procedure is thus considered to give nearly optimum size and distribution of the particles in regard to maximum corrosion resistance of the alloy.
  • a so-called final annealing of the material- is normally done.
  • the final annealing is done within the temperature range 400 700C, at which in Zircaloy an annealing at temperatures between 400 to about 490 C. gives a recovered structure, annealing between about 490 to about 530 C. gives a partially recrystallized structure, and annealing at higher temperatures gives a completely recrystallized structure.
  • the degree of reduction in the last cold working step influences the creep strength in the same way as without B-quenching.
  • the effect according to the invention is additive to the conventional effect of cold work, these being an incentive for high degree of cold work from production economy point of view. It has thus been found advantageous to reduce the cross-sectional area of the material at least 50 percent in the last cold working step.
  • the properties at tensile and burst testing of tubing made according to the invention are essentially the same as in normally made tubes. There is, however, a tendency to higher strength as well as greater ductility at hot tensile testing of B-treated tubes according to the invention.
  • the test included canning tubes formed from the alloy Zircaloy 4" containing 12 1.7 percent tin, 0.18 0.24 percent iron, 0.07 0.13 percent chromium and the rest zirconium besides customary impurities.
  • the material was prepared in the normal way by means of melting, casting, hotand cold working up to and including the last but one cold working step. After this a division was done of the material so that one part was treated according to the invention, whilst the other (i.e., the reference material) was recrystallization-annealed at 675 C., after which cold rolling with 80 percent area reduction was done. Then final annealing was performed at 500 C.
  • the first-mentioned material was heated inductively to l,050 C., i.e., in the ,B-range, for 10 seconds, after which it was air cooled to room temperature.
  • the material was cold worked in a corresponding way (80 percent reduc'tion) and then final annealed at 500, 520 and 575 C. respectively.

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  • 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 Steel (AREA)

Abstract

The creep strength of a tube formed from a ''''Zircaloy'''' material is improved by prefacing the final cold working step of the manufacturing procedure by heating the material to the Beta range and then cooling to room temperature.

Description

United States Patent 1191 Hofvenstam et al.
[4 1 Feb. 11,1975
[73] Assignee: Sandvik Aktiebolag, Sandviken.
Sweden 221 Filed: Sept. 4, 1973 211 Appl. No.: 393,816
[30] Foreign Application Priority Data Sept. 5, 1972 Sweden 11435/72 [52] US. Cl. 148/115 F [51] Int. Cl C22c 15/00, C22f1/18 [58] Field of Search 148/11.5 F; 75/177 [56] References Cited UNITED STATES PATENTS 2,894,866 7/1959 Picklesimer 148/115 F 3,645,800 2/1972 Mock et al. 148/1 1.5 F 3,689,324 9/1972 Wiener et a1 148/115 F Primary Examiner-W. Stallard Attorney, Agent, or Firm-Pierce, Scheffler & Parker [57] ABSTRACT The creep strength of a tube formed from a Zircaloy material is improved by prefacing the final cold working step of the manufacturing procedure by heating the material to the B-range and then cooling to room temperature.
4 Claims, No Drawings METHOD OF MAKING TUBES AND SIMILAR PRODUCTS OF A ZIRCONIUM ALLOY The present invention relates to a method of making tubes, and other products, of zirconium alloys containing (in percent by weight) 1.2 l.7 Sn, 0.07 0.24 Fe, 0.05 0. [5 Cr, 0 0.08 Ni, 0.09 O.l6 0, balance zirconium and customary impurities, the same being known as the Zircaloys or specifically Zircaloy 2" and Zircaloy 4.
In the conventional production of Zircaloy" tubes, -for example, canning or cladding tubes used in the nuclear reactors,- after melting and casting of the material there is a step of plastic working of the ingots up to final tube dimension. The working is usually started by forging in the a-range followed by so-called B-quenching which means heating to a temperature within the B-range and quenching in water to room temperature. Then extrusion is effected in the a-range, after which cold working is done in the form of a series of pilger rollings, drawings or similar operations, usually accompanied by intermediate annealings in the a-range.
By the expression oz-range" is meant the lower temperature interval wherein the close-packed hexagonal crystal lattice is stable, while the Ii-range means the higher temperature interval wherein the body-centered cubic crystal lattice is stable. In pure zirconium the boundary between the aand B-ranges is at 862 C., while in all alloys there is a two-phase a B range at around this temperature.
While most other zirconium alloys are processed in the same way as Zircaloy," there is one exception: i.e., the zirconium-niobium alloys containing 1-5 percent Nb and up to 3 percent Sn. These alloys are specifically designed for high strength. The basic strengthening mechanism is a finely dispersed precipitation obtained through a quenchage treatment the alloys being characterized as age-hardenable. In practice, the production of these alloys includes as the last steps a heat treatment in the B- or a B-range followed by quenching in water to a martensitic structure, possible cold work for example by rolling or drawing, and aging or tempering in the a-range at around 500 C. A major concern for the zirzonium-niobium alloys is their corrosion resistance in the nuclear reactor environment. This can be improved by proper selection of temperature and time in the quench-age treatment, as is known for example from a number of patent publications, in which the procedure for reaching optimum strength and corrosion properties is clarified.
The active constituent in the zirconium-niobium alloys is a secondary phase called Li-niobium." It consists essentially ofniobium, thus requiring a high degree of segregation of niobium between the a-zirconium and B-niobiuin phases. The strong segregation provides for finely dispersed precipitation and resistance to coarsening, which is a basic prerequisite for an agehardenable alloy. In contrast to this, most other zirconium alloys, and specifically Zircaloy, have a secondary phase consisting essentially of zirconium and requiring a moderate segregation of the alloying elements tin, iron, chromium. In addition, the solubility in the a-phase of the Zircaloy" alloying elements is great compared to that of niobium. This makes the precipitation hardening in Zircaloy weak, and the alloy has never been regarded as age-hardenable. There is no known process where Zircaloy is quench-aged in the final production steps. The B-quenching described earlier is purely applied for corrosion reasons; moreover, it is done so early in the process that a possible strengthening effect is completely dissipated by the subsequent a-annealings. Instead, the conventional way of controlling the mechanical properties of Zircaloy" tubing involves choosing the degree of cold work in the final rolling step and the temperature of the final annealing to give optimum conditions. This gives awOrk-hardened and a more or less recovered and recrystallized structure.
During operation of the reactor the canning tubes are required to possess both strength and ductility. In recent years, attention has been focused on the creep strength in the transverse direction of the tube at 300 400 C. The creep strength can be improved by adjusting the degree of cold work and the final annealing temperature, but with a sacrifice in production economy.
According to the present invention it has now been found possible to reach an essentially increased creep strength in Zircaloy tubes by means of a relatively simple modification of the manufacturing procedure. This modification means essentially that a heattreatment similar to the quench-age treatment of zirconium-niobium is introduced also for Zircaloy." Quenching may replace the last intermediate or soft annealing step, or it can be done immediately before or after it. The material is thus heated up to the ,B-range. usually 860 1,250 C., and preferably to a temperature between l,000 l,l50 C., after which cooling to room temperature is done. The cooling may be done by means of quenching in water, i.e., proper B-quenching, or by air cooling. Also cooling at speeds lying between the corresponding speeds of the mentioned cooling methods may be used.
It is believed that the essentially improved creep strength is connected with the fact that the content of alloying elements in solution is increased by means of the mentioned heat-treating step according to the invention, which in its turn means an increased temperature for the maximum dynamic aging effect according to the following text.
In the earlier-mentioned Zircaloy B-quenching, which is generally done after forging, the cooling speed when quenching in water is not higher,- because of the usually relatively large billet dimension,- than that secondary phase particles are precipitated during the cooling. These particles which contain an essential part of occurring alloying elements grow during the following heating operations, at the same time as more secondary phase particles are precipitated. The content of alloying elements in solution thus becomes lower and lower during the conventional (heretofore used) manufacturing procedure.
By means of the heat-treating step according to the invention there is allotted a dissolution of secondary phase particles and the alloying elements which are bound in these particles is, therefore in solution to a larger extent than normally. Studies of so-called dynamic strain aging at plastic deformation of the Zircaloy alloy has shown that maximum dynamic aging effect, at strain rates corresponding to creep, is obtained at about 300 350 C. for material which has been manufactured in conventional ways. By the term dynamic is here meant that the aging process occurs simultaneously with the creep testing as opposed to static aging in a special aging heat-treatment before testing described in the "case of zirconiumniobium. By means of the method according to the invention it is possible to increase the temperature of the maximum ageing effect up to 400 C. byincreasing the content of alloying elements in solution. Because this aging effect probably contributes to the high creep strength, it is realized that an increase of the temperature of the maximum agingeffect means an increase of the creep strength. It is essential that the field of action of the maximum aging effect could be increased by means of the invention up to a critical'temperature level of the cladding material, at which often certain requirements regarding the strength have been specified.
The method according to the invention has not caused any depreciation of the corrosion properties, which depreciation might have been expected in view of the earlier-mentioned influence of the secondary phase particles. The normal way of procedure is thus considered to give nearly optimum size and distribution of the particles in regard to maximum corrosion resistance of the alloy.
After the last cold working step a so-called final annealing of the material-is normally done. The final annealing is done within the temperature range 400 700C, at which in Zircaloy an annealing at temperatures between 400 to about 490 C. gives a recovered structure, annealing between about 490 to about 530 C. gives a partially recrystallized structure, and annealing at higher temperatures gives a completely recrystallized structure. In the method according to the invention it has been found advantageous to locate the annealing in the range of partial recrystallization 500 530 C. The idea is that this temperature is low enough to allow a considerable portion of the alloying elements to remain in solution.
The degree of reduction in the last cold working step influences the creep strength in the same way as without B-quenching. This means that the effect according to the invention is additive to the conventional effect of cold work, these being an incentive for high degree of cold work from production economy point of view. It has thus been found advantageous to reduce the cross-sectional area of the material at least 50 percent in the last cold working step. The properties at tensile and burst testing of tubing made according to the invention are essentially the same as in normally made tubes. There is, however, a tendency to higher strength as well as greater ductility at hot tensile testing of B-treated tubes according to the invention.
In the following text there is an example of the improved results which have been obtained by means of the'new manufacturing procedure. The test included canning tubes formed from the alloy Zircaloy 4" containing 12 1.7 percent tin, 0.18 0.24 percent iron, 0.07 0.13 percent chromium and the rest zirconium besides customary impurities. The material was prepared in the normal way by means of melting, casting, hotand cold working up to and including the last but one cold working step. After this a division was done of the material so that one part was treated according to the invention, whilst the other (i.e., the reference material) was recrystallization-annealed at 675 C., after which cold rolling with 80 percent area reduction was done. Then final annealing was performed at 500 C. The first-mentioned material was heated inductively to l,050 C., i.e., in the ,B-range, for 10 seconds, after which it was air cooled to room temperature. The material was cold worked in a corresponding way (80 percent reduc'tion) and then final annealed at 500, 520 and 575 C. respectively. I
The material prepared according to the invention and the reference material were then among other things subjected to corrosion'testing and mechanical testing. Creep tests under an inside overpressure at 400 C. during certain times showed the following average values concerning the so-called transverse creep strain (the mentioned temperature values relative to final annealing):
Material made according to the Reference invention 500C 520C 575C 500C Creep strain 0.20 0.15 0.20 1.20
- the material which had been treated according to the invention. Hot tensile testing at 400 C. gave results of somewhat higher strength and ductility of the B-treated" material, while the corresponding properties at room temperature were roughly equivalent.
We claim: I
1. ln a method of making tubes and other products with improved creep strength from a zirconium alloy containing, in Wt. percent, 1.2 1.7 Sn, 0.07 0.24 Fe, 0.05 0. l 5 Cr, 0 0.08 Ni, 0.09 0.16 0, said material having B-phase respectively a-phase structure at high respectively low temperatures, the tube or corresponding product being plastically worked to final dimension by means of hot and cold working, in which the cold working includes several steps with intermediate recrystallization annealings, the improved procedure which consists in heating the material, before the last cold working step, to the [cl-range and then cooling it to room temperature.
2. Method according to claim 1, wherein before the last col'd working step the-material is heated to a temperature between 860 l,250 C. and preferably to a temperature between l,000 l,l50 C.
3. Method according to claim 1, wherein the material after the last cold working step is annealed in the temperature range 400 700 C. and preferably in the temperature range 500 530 C.
4. Method according to claim 1, wherein the crosssectional area of material in the last cold working step is reduced at least 50 percent.

Claims (4)

1. IN A METHOD OF MAKING TUBES AND OTHER PRODUCTS WITH IMPROVED CREEP STRENGTH FROM A ZIRCONIUM ALLOY CONTAINING, IN WT. PERCENT, 1.2-1.7 SN, 0.07-0.24 FE, 0.05-0.15 CR, 00.08 NI, 0.09-0.16 O, SAID MATERIAL HAVING B-PHASE RESPECTIVELY A-PHASE STRUCTURE AT HIGH RESPECTIVELY LOW TEMPERATURES, THE TUBE OR CORRESPONDING PRODUCT BEING PLASTICALLY WORKED TO FINAL DIMENSION BY MEANS OF HOT AND COLD WORKING, IN WHICH THE COLD WORKING INCLUDES SEVERAL STEPS WITH INTERMEDIATE RECRYSTALLIZATION ANNEALINGS, THE IMPRIVED PROCEDURE WHICH CONSISTS IN HEATING THE MATERIAL, BEFORE THE LEAST COLD WORKING STEP, TO THE B-RANGE AND THEN COOLING IT TO ROOM TEMPERATURE.
2. Method according to claim 1, wherein before the last cold working step the material is heated to a temperature between 860* - 1,250* C. and preferably to a temperature between 1,000* -1,150* C.
3. Method according to claim 1, wherein the material after the last cold working step is annealed in the temperature range 400* - 700* C. and preferably in the temperature range 500* - 530* C.
4. Method according to claim 1, wherein the cross-sectional area of material in the last cold working step is reduced at least 50 percent.
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Cited By (41)

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DE2607146A1 (en) * 1975-02-25 1976-09-02 Gen Electric STRUCTURAL COMPONENTS FROM A ZIRCONALY ALLOY AND METHOD FOR HEAT TREATMENT
DE2651870A1 (en) * 1975-11-17 1977-05-18 Gen Electric Zirconium alloy for use in boiling water nuclear reactors - subjected to soln. and ageing heat treatments to improve corrosion resistance
US4108687A (en) * 1975-12-12 1978-08-22 Ugine Aciers Process for improving the heat resistance of zirconium and its alloys
US4197145A (en) * 1974-12-23 1980-04-08 General Electric Company Zirconium-base alloy structural component for nuclear reactor and method
US4238251A (en) * 1977-11-18 1980-12-09 General Electric Company Zirconium alloy heat treatment process and product
DE3003610A1 (en) * 1979-06-04 1980-12-11 Gen Electric METHOD FOR PRODUCING A CONTAINER TUBE FOR NUCLEAR FUEL ELEMENTS
US4279667A (en) * 1978-12-22 1981-07-21 General Electric Company Zirconium alloys having an integral β-quenched corrosion-resistant surface region
US4294631A (en) * 1978-12-22 1981-10-13 General Electric Company Surface corrosion inhibition of zirconium alloys by laser surface β-quenching
US4360389A (en) * 1975-11-17 1982-11-23 General Electric Company Zirconium alloy heat treatment process
JPS5822364A (en) * 1981-07-29 1983-02-09 Hitachi Ltd Preparation of zirconium base alloy
EP0085552A2 (en) * 1982-01-29 1983-08-10 Westinghouse Electric Corporation Improvements in or relating to zirconium alloys
DE3312803A1 (en) * 1982-04-15 1984-05-03 General Electric Co., Schenectady, N.Y. ZIRCONIUM ALLOY TUBE AND METHOD FOR PRODUCING IT
US4450016A (en) * 1981-07-10 1984-05-22 Santrade Ltd. Method of manufacturing cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors
US4450020A (en) * 1982-07-01 1984-05-22 Santrade Ltd. Method of manufacturing cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors
US4584030A (en) * 1982-01-29 1986-04-22 Westinghouse Electric Corp. Zirconium alloy products and fabrication processes
JPS61143571A (en) * 1985-11-22 1986-07-01 Hitachi Ltd Manufactur of zirconium alloy
FR2575764A1 (en) * 1985-01-10 1986-07-11 Cezus Co Europ Zirconium Process for the manufacture of a strip made of zirconium zircaloy 2 or restored zircaloy 4 alloy, and strip obtained
FR2576322A1 (en) * 1985-01-22 1986-07-25 Westinghouse Electric Corp PROCESS FOR FORMING ARTICLES FROM ZIRCONIUM ALLOYS
DE3609074A1 (en) * 1985-03-19 1986-10-02 Compagnie Européenne du Zirconium Cezus, Courbevoie METHOD FOR PRODUCING COMPOSITE COVER TUBES FOR NUCLEAR FUELS AND PRODUCTS OBTAINED THEREFORE
EP0198570A2 (en) * 1985-01-22 1986-10-22 Westinghouse Electric Corporation Process for producing a thin-walled tubing from a zirconium-niobium alloy
FR2580524A1 (en) * 1985-02-13 1986-10-24 Westinghouse Electric Corp PROCESS FOR MAKING SOLDER-FREE TUBES OR WITHOUT SOLDER CORDS OF METALS OR NON-FERROUS ALLOYS
FR2585593A1 (en) * 1985-08-02 1987-02-06 Westinghouse Electric Corp METHOD FOR MANUFACTURING A METAL TUBE AND TUBE THUS OBTAINED, IN PARTICULAR THE TREATMENT OF NUCLEAR FUEL TANKS
US4648912A (en) * 1982-01-29 1987-03-10 Westinghouse Electric Corp. High energy beam thermal processing of alpha zirconium alloys and the resulting articles
EP0213771A2 (en) * 1985-08-02 1987-03-11 Westinghouse Electric Corporation Improvements in or relating to annealing metal tubing
US4664727A (en) * 1982-06-21 1987-05-12 Hitachi, Ltd. Zirconium alloy having superior corrosion resistance
US4678521A (en) * 1981-07-29 1987-07-07 Hitachi, Ltd. Process for producing zirconium-based alloy and the product thereof
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
US4717434A (en) * 1982-01-29 1988-01-05 Westinghouse Electric Corp. Zirconium alloy products
US4770847A (en) * 1982-06-01 1988-09-13 General Electric Company Control of differential growth in nuclear reactor components by control of metallurgical conditions
FR2622210A1 (en) * 1987-10-23 1989-04-28 Haynes Int Inc IMPROVED PROCESS FOR FORMING SOLDER-FREE TUBES AND OTHER TITANIUM ALLOY PRODUCTS
US4908071A (en) * 1985-03-12 1990-03-13 Santrade Limited Method of manufacturing tubes of zirconium alloys with improved corrosion resistance for thermal nuclear reactors
EP0425465A1 (en) * 1989-10-27 1991-05-02 Sandvik Aktiebolag A method of manufacturing cladding tubes for fuel rods for nuclear reactors
US5112573A (en) * 1989-08-28 1992-05-12 Westinghouse Electric Corp. Zirlo material for light water reactor applications
EP0533186A1 (en) * 1991-09-20 1993-03-24 Hitachi, Ltd. Fuel assembly and components thereof
US5230758A (en) * 1989-08-28 1993-07-27 Westinghouse Electric Corp. Method of producing 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
US5305359A (en) * 1993-05-13 1994-04-19 General Electric Company Dimensionally stable and corrosion-resistant fuel channels and related method of manufacture
US5361282A (en) * 1993-05-13 1994-11-01 General Electric Company Dimensionally stable and corrosion-resistant fuel channels and related method of manufacture
US5876524A (en) * 1994-06-22 1999-03-02 Sandvik Ab Method for the manufacture of tubes of a zirconium based alloy for nuclear reactors and their usage
WO2000029633A1 (en) * 1998-11-12 2000-05-25 Westinghouse Atom Ab Method of manufacturing a zirconium based alloy component for use in nuclear industry
US20060215806A1 (en) * 2003-07-31 2006-09-28 Pierre Barberis Method for making a flat zirconium alloy product, resulting flat product and fuel, assembly component for nuclear power plant reactor made from said flat product

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US3645800A (en) * 1965-12-17 1972-02-29 Westinghouse Electric Corp Method for producing wrought zirconium alloys
US3689324A (en) * 1968-09-27 1972-09-05 George W Wiener Process for obtaining preferred orientation in zirconium and its alloy

Cited By (57)

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US4197145A (en) * 1974-12-23 1980-04-08 General Electric Company Zirconium-base alloy structural component for nuclear reactor and method
DE2607146A1 (en) * 1975-02-25 1976-09-02 Gen Electric STRUCTURAL COMPONENTS FROM A ZIRCONALY ALLOY AND METHOD FOR HEAT TREATMENT
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