[go: up one dir, main page]

US20060081313A1 - Method for the production of a semi-finished product made of zirconium alloy for the production of a flat product and use thereof - Google Patents

Method for the production of a semi-finished product made of zirconium alloy for the production of a flat product and use thereof Download PDF

Info

Publication number
US20060081313A1
US20060081313A1 US10/541,262 US54126205A US2006081313A1 US 20060081313 A1 US20060081313 A1 US 20060081313A1 US 54126205 A US54126205 A US 54126205A US 2006081313 A1 US2006081313 A1 US 2006081313A1
Authority
US
United States
Prior art keywords
production
alloy
zirconium alloy
zirconium
ingot
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.)
Abandoned
Application number
US10/541,262
Inventor
Pierre Barberis
Neol Rizzi
Xavier Robbe
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.)
Compagnie Europeenne du Zirconium Cezus SA
Original Assignee
Compagnie Europeenne du Zirconium Cezus SA
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 Compagnie Europeenne du Zirconium Cezus SA filed Critical Compagnie Europeenne du Zirconium Cezus SA
Assigned to COMPAGNIE EUROPEENNE DU ZIRCONIUM-CEZUS reassignment COMPAGNIE EUROPEENNE DU ZIRCONIUM-CEZUS ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: RIZZI, JOSEPH NOEL, ROBBE, XAVIER, BARBERIS, PIERRE
Publication of US20060081313A1 publication Critical patent/US20060081313A1/en
Abandoned legal-status Critical Current

Links

Images

Classifications

    • 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
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C16/00Alloys based on zirconium
    • 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

Definitions

  • the invention relates to a method for the production of a semi-finished product made of zirconium alloy intended for the production of a flat product used for the manufacture of fuel assembly elements.
  • Fuel assemblies in nuclear reactors cooled by light water for example pressurized water reactors (PWR) and boiling water reactors (BWR), or fuel assemblies of CANDU reactors, contain elements comprising a zirconium alloy with the property of low neutron absorption in the heart of the nuclear reactor.
  • PWR pressurized water reactors
  • BWR boiling water reactors
  • CANDU reactors fuel assemblies of CANDU reactors
  • the jacket tubes for the fuel rods and the plates used for production of the spacer grids for the fuel assembly can be made of zirconium alloy, in particular zirconium alloy containing tin and iron such as the alloys Zircaloy 2 or Zircaloy 4.
  • the parallelepipedic housings of the fuel assemblies for BWR reactors are also generally produced from flat products of zirconium alloys such as Zircaloy 2 or Zircaloy 4.
  • alloys such as the alloy known under the commercial name M5, which essentially comprises zirconium and niobium, are also used for the production of fuel assembly elements in the form of flat or tubular products.
  • the zirconium alloys used for the production of fuel assembly elements comprise at least 97% zirconium by weight, the remainder of the composition which represents at most 3% by weight, with the exception of impurities due to the production of the alloy, can comprise various elements and in particlar iron, tin or niobium.
  • Zirconium alloys meeting these conditions in relation to their composition, depending on the temperature and the heat treatment to which they are subjected, can take one or the other of the two allotropic forms of zirconium i.e. the alpha phase, which is the phase of zirconium stable at low temperature with a compact hexagonal structure, or the beta phase, which is the phase stable at high temperature with a cubic structure.
  • the alpha phase which is the phase of zirconium stable at low temperature with a compact hexagonal structure
  • beta phase which is the phase stable at high temperature with a cubic structure.
  • zirconium alloys such as the technical alloys used for the production of fuel assembly elements defined above can have a mixed alpha+beta structure.
  • Flat products of zirconium alloy are generally produced by numerous successive stages of hot and cold forming and heat treatment.
  • the starting product is usually a very large ingot obtained by casting an alloy set to the required composition.
  • an ingot is cast with a diameter for example between 400 and 800 mm, and a length between 2 m and 3 m.
  • the ingot then undergoes forging operations in a temperature range in which it can be in the ⁇ , ⁇ or ⁇ + ⁇ phase (EP-0.085.552 and U.S. Pat. No. 5,674,330).
  • the ingot is heated so that the alloy is in the beta phase, then a first forging stage is performed on the heated ingot in the beta phase.
  • the ingot can be heated to 1050° C. for ten hours before forging.
  • the product resulting from the forging is quenched from the beta phase.
  • the resulting product which constitutes the semi-finished product of the process for producing a flat product is a slab which can have a thickness of the order of 100 mm.
  • the slab is then subjected to various hot rolling and cold rolling operations to obtain a flat end product such as a strip with a thickness of 0.2 to 4 mm.
  • the heat treatments of quenching and annealing are performed between at least certain of the forming operations of the flat end product.
  • the transformation process which has just been described comprises numerous phases of successive treatments and in particular several quenchings from the beta phase to obtain the semi-finished product such as a slab which is hot formed, and the second intermediate product which is cold formed.
  • the zirconium alloy product comes into contact with humid air and/or water so that it absorbs hydrogen which fixes in the material in the form of hydrides.
  • Hydrides are generally precipitated in a temperature range from 220° C. to 100° C. during the cooling of the product, and the hydrides form in a quantity which is larger and in a form which is coarser as the material absorbs more hydrogen.
  • French patent 2,334,763 proposes a process of heat treatment and/or thermomechanical treatment of a zirconium alloy containing over 150 ppm carbon in a temperature range between 830° C. and 950° C. in order to solubilise at least part of the carbon, no subsequent heat treatment being performed at a temperature greater than 950° C.
  • the heat treatment or thermomechanical treatment in the temperature range of 830° C. to 950° C., which corresponds to the range in which the alpha and beta phases are present in the alloy, is only performed after a first forging of an ingot in the beta phase followed by quenching in water.
  • the objective of the present invention is to propose a method for production of a zirconium alloy semi-finished product containing by weight at least 97% zirconium and intended for the production of flat products, in which a large ingot is produced by casting the zirconium alloy, then by forging the large ingot a semi-finished product intended to be hot rolled then cold rolled to obtain the flat product is produced, heat treatments of quenching and annealing being interspersed between at least certain of the forming operations, where this method simplifies and reduces the cost of production of the product, and limits to low levels the presence of hydrides which have a harmful effect on the formability and corrosion resistance of the zirconium alloy product.
  • the semi-finished product is produced from the large cast ingot by a single forging operation at a temperature at which the zirconium alloy is in a state comprising the crystalline ⁇ and ⁇ phases of the zirconium alloy.
  • the invention also relates to the use of the method for production of a slab intended for production of a flat product of a thickness between 0.2 mm and 4 mm for the manufacture of a nuclear fuel assembly element such as a plate of a spacer grid for the fuel assembly of a PWR reactor or a wall of a fuel assembly housing for a BWR reactor or again a fuel assembly element for a CANDU reactor.
  • a nuclear fuel assembly element such as a plate of a spacer grid for the fuel assembly of a PWR reactor or a wall of a fuel assembly housing for a BWR reactor or again a fuel assembly element for a CANDU reactor.
  • FIG. 1 is a diagram showing in a symbolic manner the various stages of the production method of the prior art.
  • FIG. 2 is a diagrammatic representation similar to that in FIG. 1 of the production method according to the invention serving to produce the semi-finished product.
  • FIG. 1 shows a cast ingot 1 which can be a large ingot, the diameter of which can be between 400 mm and 800 mm and the length between 2 m and 3 m, which is obtained by casting a zirconium alloy used for the production of flat products for the manufacture of fuel assembly elements.
  • the zirconium alloy can be for example a Zircaloy 2 alloy comprising in weight from 1.2% to 1.7% tin, 0.07% to 0.20% iron, 0.05% to 0.15% chromium, 0.03% to 0.08% nickel, at most 120 ppm silicon and 150 ppm carbon, the remainder of the alloy being constituted by zirconium with the exception of the usual impurities.
  • the alloy for production of the flat product can be also a Zircaloy 4 comprising by weight 1.2% to 1.7% tin, 0.18% to 0.24% iron, 0.07% to 0.13% chromium, at most 150 ppm carbon, the remainder of the alloy being constituted by zirconium and impurities.
  • the alloy is cast as a large ingot 1 which is then brought to a temperature higher than 1000° C. and for example a temperature of 1050° C. for ten hours so that the alloy of the ingot is entirely in the beta cubic phase, stable at high temperature.
  • the cast ingot is then forged at a temperature in the beta range of the alloy and for example at a temperature close to 1000° C. in the form of a flat product of substantial thickness known as a slab, as shown by stage 2 on FIG. 1 .
  • the thick slab 3 then undergoes quenching in water or humid air as shown symbolically by the arrows representing a third stage 4 of the production process.
  • the thick slab 3 is forged at a temperature in the alpha range of the zirconium alloy, for example at a temperature of the order of 800° C.
  • the initial forging of the ingot 1 in the beta phase must be followed by quenching in the beta phase (stage 2 of the process) as the metal, which cools during forging, can contain an external zone in the alpha+beta phase leading to the formation of segregations of alphagenic elements such as tin and oxygen and betagenic elements such as iron, chromium, nickel or niobium, depending on the elements contained in the alloy.
  • alphagenic elements such as tin and oxygen
  • betagenic elements such as iron, chromium, nickel or niobium
  • Quenching in the beta phase entails the slab 3 coming into contact with a quenching environment constituted by water or humid air, i.e. an environment containing hydrogen.
  • Hydrogen is absorbed by the slab at the time of heat treatment and fixes inside the alloy in the form of hydrides.
  • the large cast ingot 1 of zirconium alloy is subjected to a single forging operation 7 in the ⁇ + ⁇ phase to obtain the slab 8 substantially similar to the slab 3 obtained by the complex forging process in the ⁇ phase, quenching from the ⁇ phase and forging in the ⁇ phase.
  • the method according to the invention thus comprises replacing the three first stages 2, 4 and 5 of the process of the prior art, i.e. stage 2 of forging in the beta phase (above 1000° C.) followed by stage 4 of quenching the slab 3 ′ from the beta phase and forging in the alpha phase at a temperature below 800° C., with a single stage 7 of forging in the alpha+beta phase, for example in the case of alloys Zircaloy 2 and 4, at a temperature between 850° C. and 950° C. and for example at a temperature of the order of 900° C.
  • the temperature for the ⁇ + ⁇ phase forging is selected so that the volume proportion of the ⁇ phase in the ingot alloy is between 10% and 90%, the remainder of the alloy being in the ⁇ phase.
  • the ingot 1 is forged to give a slab 8 of thickness which can be of the order of 100 mm and which constitutes the semi-finished product that will then be subjected to the operations of hot rolling and cold rolling as described above, separated by stages of quenching and annealing as heat treatment.
  • the quantity of hydrides contained in the alloy obtained by the process according to the invention is substantially smaller than the quantity of hydrides contained in a product according to the prior art.
  • the hydrides precipitated in the product according to the invention are also of a size generally smaller than the hydrides precipitated in a flat product according to the prior art.
  • one of the advantages of the method according to the invention is to simplify considerably the process of production of the semi-finished product. This therefore leads to a substantial reduction in cost and duration in the implementation of the process.
  • the product is only brought to a temperature in the ⁇ and ⁇ range, i.e. a temperature markedly lower than the sustained temperature in the ⁇ phase of the process in the prior art.
  • the forging of the ingot 1 in the ⁇ + ⁇ phase is performed in a temperature interval ranging from 850° C. to 950° C. and for example at 900° C.
  • the transition to the ⁇ + ⁇ phase of the alloy, to perform the forging of the method according to the invention can lead to the formation of tin segregations.
  • the forging temperature in the ⁇ + ⁇ phase can be substantially lower than 900° C. taking into account however the malleability properties of the alloy at the forging temperature.
  • zirconium alloys other than Zircaloy or to niobium alloys can be considered.
  • These alloys generally contain at most 3% in weight of additive elements comprising at least one of the additive elements tin, iron, chromium, nickel, oxygen, niobium, vanadium and silicon, the remainder of the alloy being constituted by zirconium and the inevitable impurities.
  • the invention applies in particular to the production of a flat product of zirconium alloy for the manufacture of fuel assembly elements such as plates for the manufacture of spacer grids for assemblies for PWR-type nuclear reactors or housing walls for assemblies for BWR reactors or for fuel assembly elements for CANDU reactors.
  • the temperature for forging in the ⁇ + ⁇ phase depends on the composition of the zirconium alloy.
  • the forging operations can be performed using the normal means for forging in the ⁇ phase or ⁇ phase of the process of the prior art or other means adapted to ⁇ + ⁇ phase forging in a single operation to obtain a slab.
  • the invention applies generally to any technical zirconium alloy product defined by the composition limits given above.

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Forging (AREA)

Abstract

A large ingot is produced by casting the zirconium alloy, then the ingot is forged to obtain the semi-finished product wherein the semi-finished product can be a slab for production of a flat product is produced from the large cast ingot in a single forging operation at a temperature at which the zirconium alloy is in a state comprising both the crystalline α and β phases of the alloy.

Description

    FIELD OF THE INVENTION
  • The invention relates to a method for the production of a semi-finished product made of zirconium alloy intended for the production of a flat product used for the manufacture of fuel assembly elements.
  • BACKGROUND INFORMATION
  • Fuel assemblies in nuclear reactors cooled by light water, for example pressurized water reactors (PWR) and boiling water reactors (BWR), or fuel assemblies of CANDU reactors, contain elements comprising a zirconium alloy with the property of low neutron absorption in the heart of the nuclear reactor.
  • In the case of assemblies for PWR-type nuclear reactors, the jacket tubes for the fuel rods and the plates used for production of the spacer grids for the fuel assembly can be made of zirconium alloy, in particular zirconium alloy containing tin and iron such as the alloys Zircaloy 2 or Zircaloy 4.
  • The parallelepipedic housings of the fuel assemblies for BWR reactors are also generally produced from flat products of zirconium alloys such as Zircaloy 2 or Zircaloy 4.
  • Other alloys such as the alloy known under the commercial name M5, which essentially comprises zirconium and niobium, are also used for the production of fuel assembly elements in the form of flat or tubular products.
  • In general the zirconium alloys used for the production of fuel assembly elements comprise at least 97% zirconium by weight, the remainder of the composition which represents at most 3% by weight, with the exception of impurities due to the production of the alloy, can comprise various elements and in particlar iron, tin or niobium.
  • Zirconium alloys meeting these conditions in relation to their composition, depending on the temperature and the heat treatment to which they are subjected, can take one or the other of the two allotropic forms of zirconium i.e. the alpha phase, which is the phase of zirconium stable at low temperature with a compact hexagonal structure, or the beta phase, which is the phase stable at high temperature with a cubic structure.
  • In certain temperature ranges or at the end of certain treatments, zirconium alloys such as the technical alloys used for the production of fuel assembly elements defined above can have a mixed alpha+beta structure.
  • Flat products of zirconium alloy are generally produced by numerous successive stages of hot and cold forming and heat treatment.
  • The starting product is usually a very large ingot obtained by casting an alloy set to the required composition. Typically an ingot is cast with a diameter for example between 400 and 800 mm, and a length between 2 m and 3 m. The ingot then undergoes forging operations in a temperature range in which it can be in the α, β or α+β phase (EP-0.085.552 and U.S. Pat. No. 5,674,330).
  • Preferably the ingot is heated so that the alloy is in the beta phase, then a first forging stage is performed on the heated ingot in the beta phase. Typically the ingot can be heated to 1050° C. for ten hours before forging.
  • After a first forging stage, the product resulting from the forging is quenched from the beta phase.
  • Then a second forging stage is performed at a temperature below 800° C., the alloy being in the alpha phase, in the case of Zircaloy-type alloys. After the second forging stage, the resulting product which constitutes the semi-finished product of the process for producing a flat product, is a slab which can have a thickness of the order of 100 mm.
  • The slab is then subjected to various hot rolling and cold rolling operations to obtain a flat end product such as a strip with a thickness of 0.2 to 4 mm. The heat treatments of quenching and annealing are performed between at least certain of the forming operations of the flat end product.
  • The transformation process which has just been described comprises numerous phases of successive treatments and in particular several quenchings from the beta phase to obtain the semi-finished product such as a slab which is hot formed, and the second intermediate product which is cold formed.
  • During the cooling stages of the products or during the quenching stages, the zirconium alloy product comes into contact with humid air and/or water so that it absorbs hydrogen which fixes in the material in the form of hydrides.
  • In general the presence of hydrides in the material in the form of coarse precipitates is harmful to the cold formability and corrosion resistance of the products.
  • Hydrides are generally precipitated in a temperature range from 220° C. to 100° C. during the cooling of the product, and the hydrides form in a quantity which is larger and in a form which is coarser as the material absorbs more hydrogen.
  • Because it is advantageous to limit the formation of hydrides in the material or promote the preferential formation of hydrides in fine form, it is preferable to perform the transformation processes of the zirconium alloy products such that these products absorb the smallest possible quantity of hydrogen during the forming and heat treatment operations.
  • It is also advantageous to be able to simplify the forming process which is complex and comprises numerous successive operations.
  • French patent 2,334,763 proposes a process of heat treatment and/or thermomechanical treatment of a zirconium alloy containing over 150 ppm carbon in a temperature range between 830° C. and 950° C. in order to solubilise at least part of the carbon, no subsequent heat treatment being performed at a temperature greater than 950° C.
  • The heat treatment or thermomechanical treatment in the temperature range of 830° C. to 950° C., which corresponds to the range in which the alpha and beta phases are present in the alloy, is only performed after a first forging of an ingot in the beta phase followed by quenching in water.
  • The process according to French patent 2,334,763 is only suitable for zirconium alloys of a particular type and does not allow modification of the first phases of production of products during which water quenching is performed. Furthermore, production stages after the heat treatment or thermomechanical treatment in the alpha+beta phase cannot be performed at a temperature above 950° C.
  • The process according to the former patent is therefore limited in its applications and the results obtained in relation to the presence of hydrides in the end product.
  • SUMMARY
  • The objective of the present invention is to propose a method for production of a zirconium alloy semi-finished product containing by weight at least 97% zirconium and intended for the production of flat products, in which a large ingot is produced by casting the zirconium alloy, then by forging the large ingot a semi-finished product intended to be hot rolled then cold rolled to obtain the flat product is produced, heat treatments of quenching and annealing being interspersed between at least certain of the forming operations, where this method simplifies and reduces the cost of production of the product, and limits to low levels the presence of hydrides which have a harmful effect on the formability and corrosion resistance of the zirconium alloy product.
  • To this end the semi-finished product is produced from the large cast ingot by a single forging operation at a temperature at which the zirconium alloy is in a state comprising the crystalline α and β phases of the zirconium alloy.
  • According to particular features:
      • at the forging temperature, the ingot comprises a volume proportion of zirconium alloy in the α phase between 10% and 90%, the rest of the zirconium alloy of the ingot being in the β phase,
      • the semi-finished product is a slab;
      • the slab has a thickness of around 100 mm and is intended for production of a flat product having a thickness between 0.2 mm and 4 mm;
      • the forging of the zirconium alloy in the α and β phase is performed at a temperature between 850° C. and 950° C.; and
      • the zirconium alloy comprises at least 3% by weight in total of additional elements comprising at least one of the elements tin, iron, chromium, nickel, oxygen, niobium, vanadium and silicon, the remainder of the alloy being constituted by zirconium with the exception of the inevitable impurities.
  • The invention also relates to the use of the method for production of a slab intended for production of a flat product of a thickness between 0.2 mm and 4 mm for the manufacture of a nuclear fuel assembly element such as a plate of a spacer grid for the fuel assembly of a PWR reactor or a wall of a fuel assembly housing for a BWR reactor or again a fuel assembly element for a CANDU reactor.
  • In order to understand the invention, in a comparison a production method will be 20 described for a semi-finished product intended for production of flat products according to the prior art and according to the invention.
  • BRIEF DESCRIPTION OF THE DRAWINGS
  • FIG. 1 is a diagram showing in a symbolic manner the various stages of the production method of the prior art.
  • FIG. 2 is a diagrammatic representation similar to that in FIG. 1 of the production method according to the invention serving to produce the semi-finished product.
  • DETAILED DESCRIPTION
  • FIG. 1 shows a cast ingot 1 which can be a large ingot, the diameter of which can be between 400 mm and 800 mm and the length between 2 m and 3 m, which is obtained by casting a zirconium alloy used for the production of flat products for the manufacture of fuel assembly elements.
  • DETAILED DESCRIPTION
  • The zirconium alloy can be for example a Zircaloy 2 alloy comprising in weight from 1.2% to 1.7% tin, 0.07% to 0.20% iron, 0.05% to 0.15% chromium, 0.03% to 0.08% nickel, at most 120 ppm silicon and 150 ppm carbon, the remainder of the alloy being constituted by zirconium with the exception of the usual impurities.
  • The alloy for production of the flat product can be also a Zircaloy 4 comprising by weight 1.2% to 1.7% tin, 0.18% to 0.24% iron, 0.07% to 0.13% chromium, at most 150 ppm carbon, the remainder of the alloy being constituted by zirconium and impurities.
  • The alloy is cast as a large ingot 1 which is then brought to a temperature higher than 1000° C. and for example a temperature of 1050° C. for ten hours so that the alloy of the ingot is entirely in the beta cubic phase, stable at high temperature.
  • The cast ingot is then forged at a temperature in the beta range of the alloy and for example at a temperature close to 1000° C. in the form of a flat product of substantial thickness known as a slab, as shown by stage 2 on FIG. 1.
  • The thick slab 3 then undergoes quenching in water or humid air as shown symbolically by the arrows representing a third stage 4 of the production process.
  • In a fourth stage indicated by 5 in FIG. 1, the thick slab 3 is forged at a temperature in the alpha range of the zirconium alloy, for example at a temperature of the order of 800° C.
  • This gives a slab 3 with a thickness of the order of 100 mm which constitutes the semi-finished product from the forging and undergoes hot rolling then cold rolling to obtain the flat end product in the form of a sheet or strip of a thickness which can be between 0.2 mm and 4 mm.
  • The initial forging of the ingot 1 in the beta phase (stage 2 of the process) must be followed by quenching in the beta phase (stage 2 of the process) as the metal, which cools during forging, can contain an external zone in the alpha+beta phase leading to the formation of segregations of alphagenic elements such as tin and oxygen and betagenic elements such as iron, chromium, nickel or niobium, depending on the elements contained in the alloy.
  • These segregations are harmful to the properties of use of the alloy and in particular the properties of corrosion resistance and suitability for deep drawing.
  • Quenching in the beta phase entails the slab 3 coming into contact with a quenching environment constituted by water or humid air, i.e. an environment containing hydrogen.
  • Hydrogen is absorbed by the slab at the time of heat treatment and fixes inside the alloy in the form of hydrides.
  • The forming suitability and corrosion resistance of the flat product of zinc alloy consequently deteriorate.
  • The method according to the invention for the production of a slab intended for the production of flat products will be described in relation to FIG. 2.
  • The large cast ingot 1 of zirconium alloy is subjected to a single forging operation 7 in the α+β phase to obtain the slab 8 substantially similar to the slab 3 obtained by the complex forging process in the β phase, quenching from the β phase and forging in the α phase.
  • The method according to the invention thus comprises replacing the three first stages 2, 4 and 5 of the process of the prior art, i.e. stage 2 of forging in the beta phase (above 1000° C.) followed by stage 4 of quenching the slab 3′ from the beta phase and forging in the alpha phase at a temperature below 800° C., with a single stage 7 of forging in the alpha+beta phase, for example in the case of alloys Zircaloy 2 and 4, at a temperature between 850° C. and 950° C. and for example at a temperature of the order of 900° C.
  • The temperature for the α+β phase forging is selected so that the volume proportion of the α phase in the ingot alloy is between 10% and 90%, the remainder of the alloy being in the β phase.
  • The ingot 1 is forged to give a slab 8 of thickness which can be of the order of 100 mm and which constitutes the semi-finished product that will then be subjected to the operations of hot rolling and cold rolling as described above, separated by stages of quenching and annealing as heat treatment.
  • By performing analyses on the semi-finished product 8 or on the flat products obtained from the semi-finished product, it can be observed that the quantity of hydrides contained in the alloy obtained by the process according to the invention is substantially smaller than the quantity of hydrides contained in a product according to the prior art.
  • On the semi-finished product which is a slab in the case of production of flat products, a hydrogen content has been measured which is twice as low as in the process of the prior art, when forging in the α+β phase is used instead of the three initial stages of the production process according to the prior art.
  • The hydrides precipitated in the product according to the invention are also of a size generally smaller than the hydrides precipitated in a flat product according to the prior art.
  • The properties of corrosion resistance and formability of the flat product made from the semi-finished product obtained according to the invention are therefore markedly superior to those of a product obtained in the process according to conventional processes.
  • These advantageous and surprising results may be due to the absence of high temperature quenching on a slab obtained by forging in the p phase.
  • In fact this high temperature quenching on the slab 3′ which is achieved with a quenching medium containing hydrogen produces an absorption of hydrogen by the product and the subsequent formation of hydrides.
  • Also one of the advantages of the method according to the invention is to simplify considerably the process of production of the semi-finished product. This therefore leads to a substantial reduction in cost and duration in the implementation of the process.
  • Also the product is only brought to a temperature in the α and β range, i.e. a temperature markedly lower than the sustained temperature in the β phase of the process in the prior art.
  • In the case of the Zircaloy 2 and Zircaloy 4 alloys of which the composition is given above, the forging of the ingot 1 in the α+β phase is performed in a temperature interval ranging from 850° C. to 950° C. and for example at 900° C.
  • In the case of the Zircaloy 2 and Zircaloy 4 alloys or any other alloy containing tin, the transition to the α+β phase of the alloy, to perform the forging of the method according to the invention, can lead to the formation of tin segregations.
  • However, these segregations can be suppressed by subsequent processing within the context of production of the flat end product from the semi-finished product.
  • In the case where the process of the invention is applied to niobium alloys, in which the transition between the α and α+β phases is close to 600° C., the forging temperature in the α+β phase can be substantially lower than 900° C. taking into account however the malleability properties of the alloy at the forging temperature.
  • Application of the process according to the invention to zirconium alloys other than Zircaloy or to niobium alloys can be considered. These alloys generally contain at most 3% in weight of additive elements comprising at least one of the additive elements tin, iron, chromium, nickel, oxygen, niobium, vanadium and silicon, the remainder of the alloy being constituted by zirconium and the inevitable impurities.
  • The invention applies in particular to the production of a flat product of zirconium alloy for the manufacture of fuel assembly elements such as plates for the manufacture of spacer grids for assemblies for PWR-type nuclear reactors or housing walls for assemblies for BWR reactors or for fuel assembly elements for CANDU reactors.
  • The invention is not limited strictly to the embodiments described.
  • The temperature for forging in the α+β phase depends on the composition of the zirconium alloy. The forging operations can be performed using the normal means for forging in the α phase or β phase of the process of the prior art or other means adapted to α+β phase forging in a single operation to obtain a slab.
  • The invention applies generally to any technical zirconium alloy product defined by the composition limits given above.

Claims (6)

1-5. (canceled)
6. A method for production of a semi-finished product made of zirconium alloy containing by weight at least 97% zirconium, intended for the production of flat products, comprising:
producing an ingot with a diameter between 400 mm and 800 mm and a length between 2 m and 3 m by casting the zirconium alloy;
forging the ingot of the semi-finished product in the form of a slab with a thickness of approximately 100 mm and intended to be hot rolled then cold rolled to obtain a flat product of a thickness between 0.2 mm and 4 mm, wherein the slab is produced from the ingot by a single forging operation at a temperature at which the zirconium alloy is in a state comprising the crystalline α and β phases of the zirconium alloy.
7. The method according to claim 6, wherein at the forging temperature the ingot contains a volume proportion of zirconium alloy in the α phase between 10% and 90%, a remainder of the zirconium alloy of the ingot being in the β phase.
8. The method according to claim 6, wherein the forging of the zirconium alloy in the α and β phase is performed at a temperature between 850° C. and 950° C.
9. The method according to claim 6, wherein the zirconium alloy contains at least 3% by weight in total of additive elements comprising at least one of the elements tin, iron, chromium, nickel, oxygen, niobium, vanadium and silicon, a remainder of the alloy being constituted by zirconium with an exception of inevitable impurities.
10. The method according to claim 6, wherein during production of the slab a flat product of a thickness between 0.2 mm and 4 mm is produced for a nuclear fuel assembly.
US10/541,262 2003-01-13 2004-01-09 Method for the production of a semi-finished product made of zirconium alloy for the production of a flat product and use thereof Abandoned US20060081313A1 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
FR0300316 2003-01-13
FR0300316A FR2849865B1 (en) 2003-01-13 2003-01-13 PROCESS FOR THE PRODUCTION OF A ZIRCONIUM ALLOY PRODUCT FOR THE PRODUCTION OF A FLAT PRODUCT AND USE THEREOF
PCT/FR2004/000036 WO2004072318A1 (en) 2003-01-13 2004-01-09 Method for the production of a semi-finished product made of zirconium alloy for the production of a flat product and use thereof

Publications (1)

Publication Number Publication Date
US20060081313A1 true US20060081313A1 (en) 2006-04-20

Family

ID=32524867

Family Applications (1)

Application Number Title Priority Date Filing Date
US10/541,262 Abandoned US20060081313A1 (en) 2003-01-13 2004-01-09 Method for the production of a semi-finished product made of zirconium alloy for the production of a flat product and use thereof

Country Status (8)

Country Link
US (1) US20060081313A1 (en)
EP (1) EP1585841A1 (en)
JP (1) JP2006520430A (en)
KR (1) KR20050090456A (en)
CN (1) CN100529148C (en)
FR (1) FR2849865B1 (en)
RU (1) RU2337177C2 (en)
WO (1) WO2004072318A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10119181B2 (en) 2013-01-11 2018-11-06 Areva Np Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8116422B2 (en) * 2005-12-29 2012-02-14 General Electric Company LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields
JP2014077152A (en) * 2012-10-09 2014-05-01 Tohoku Univ Zr ALLOY AND ITS MANUFACTURING METHOD

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3645800A (en) * 1965-12-17 1972-02-29 Westinghouse Electric Corp Method for producing wrought zirconium alloys
US5674330A (en) * 1994-08-30 1997-10-07 Compagnie Europeene Du Zirconium Cezus Process for the production of zirconium alloy sheet metal having good resistance to nodular corrosion and to deformation under irradiation
US5844959A (en) * 1997-08-01 1998-12-01 Siemens Power Corporation Zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup
US5854818A (en) * 1997-08-28 1998-12-29 Siemens Power Corporation Zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup
US20060090821A1 (en) * 2003-01-13 2006-05-04 Pierre Barberis Method of producing a zirconium alloy semi-finished product for the production of elongated product and use thereof
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
US20070053476A1 (en) * 2003-10-08 2007-03-08 Pierre Barberis Method of producing a flat zirconium alloy product, flat product thus obtained and a nuclear plant reactor grid which is made from said flat product
US20080080660A1 (en) * 2004-08-04 2008-04-03 Pierre Barberis Method Of Manufacturing A Fuel Cladding Tube For A Nuclear Reactor, And A Tube Obtained Thereby

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2334763A1 (en) * 1975-12-12 1977-07-08 Ugine Aciers PROCESS FOR IMPROVING THE HOT RESISTANCE OF ZIRCONIUM AND ITS ALLOYS
CA1214978A (en) * 1982-01-29 1986-12-09 Samuel G. Mcdonald Zirconium alloy products and fabrication processes
ZA8383B (en) * 1982-01-29 1983-12-28 Westinghouse Electric Corp High energy beam thermal processing of alpha zirconium alloys and the resulting articles
JPH059688A (en) * 1991-07-06 1993-01-19 Kobe Steel Ltd Manufacture of zr alloy rolled stock excellent in workability
RU2110600C1 (en) * 1996-09-10 1998-05-10 Открытое акционерное общество "Чепецкий механический завод" Method for producing articles from zirconium alloys
FR2801323B1 (en) * 1999-11-23 2002-02-01 Cezus Cie Europ Du Zirconium ZIRCONIUM ALLOY WITH HIGH RESISTANCE TO CORROSION AND HYDRURATION BY WATER AND WATER VAPOR AND METHOD OF THERMOMECHANICAL TRANSFORMATION OF THE ALLOY
KR100441562B1 (en) * 2001-05-07 2004-07-23 한국수력원자력 주식회사 Nuclear fuel cladding tube of zirconium alloys having excellent corrosion resistance and mechanical properties and process for manufacturing thereof

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3645800A (en) * 1965-12-17 1972-02-29 Westinghouse Electric Corp Method for producing wrought zirconium alloys
US5674330A (en) * 1994-08-30 1997-10-07 Compagnie Europeene Du Zirconium Cezus Process for the production of zirconium alloy sheet metal having good resistance to nodular corrosion and to deformation under irradiation
US5844959A (en) * 1997-08-01 1998-12-01 Siemens Power Corporation Zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup
US5854818A (en) * 1997-08-28 1998-12-29 Siemens Power Corporation Zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup
US20060090821A1 (en) * 2003-01-13 2006-05-04 Pierre Barberis Method of producing a zirconium alloy semi-finished product for the production of elongated product and use thereof
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
US20070053476A1 (en) * 2003-10-08 2007-03-08 Pierre Barberis Method of producing a flat zirconium alloy product, flat product thus obtained and a nuclear plant reactor grid which is made from said flat product
US20080080660A1 (en) * 2004-08-04 2008-04-03 Pierre Barberis Method Of Manufacturing A Fuel Cladding Tube For A Nuclear Reactor, And A Tube Obtained Thereby

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10119181B2 (en) 2013-01-11 2018-11-06 Areva Np Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy

Also Published As

Publication number Publication date
RU2005125715A (en) 2006-02-10
CN1735705A (en) 2006-02-15
JP2006520430A (en) 2006-09-07
WO2004072318B1 (en) 2004-10-28
EP1585841A1 (en) 2005-10-19
KR20050090456A (en) 2005-09-13
CN100529148C (en) 2009-08-19
FR2849865B1 (en) 2006-01-21
WO2004072318A1 (en) 2004-08-26
RU2337177C2 (en) 2008-10-27
FR2849865A1 (en) 2004-07-16

Similar Documents

Publication Publication Date Title
KR100364093B1 (en) A method of manufacturing a tube for a nuclear fuel assembly, and tubes obtained thereby
JP2638351B2 (en) Fuel assembly
US6544361B1 (en) Process for manufacturing thin components made of zirconium-based alloy and straps thus produced
JP2731414B2 (en) Tubes, bars, sheets or strips resistant to homogeneous and nodular corrosion, and methods of making the same
JPS5822364A (en) Manufacturing method of zirconium-based alloy
JP3510211B2 (en) Cladding tube for fuel rod of pressurized water reactor and method of manufacturing the cladding tube
KR100423109B1 (en) Zirconium alloy tube for a nuclear reactor fuel assembley, and method for making same
US6884304B1 (en) Zirconium alloy highly resistant to corrosion and to sun burst by water and water vapor and method for thermomechanical transformation of the alloy
US20120145287A1 (en) Zirconium alloy compositions having excellent corrosion resistance by the control of various metal-oxide and precipitate and preparation method thereof
JPH07224373A (en) Method of improving corrosion resistance of barrier coating made of zirconium or zirconium alloy
JPH11148990A (en) Production of tube cladding nuclear fuel rod, nuclear fuel cladding, production of zirconium alloy and production of structure member
ZA200509729B (en) Zirconium alloy and components for the core of light water cooled nuclear reactors
US7763132B2 (en) Method of producing a zirconium alloy semi-finished product for the production of elongated product and use thereof
JPH01119650A (en) Manufacture of channel box for nuclear reactor fuel assembly
EP1556869B1 (en) Method, use and device concerning cladding tubes for nuclear fuel and a fuel assembly for a nuclear pressure water reactor
US20060081313A1 (en) Method for the production of a semi-finished product made of zirconium alloy for the production of a flat product and use thereof
JPS5822365A (en) Preparation of zirconium base alloy
EP0745258B1 (en) A nuclear fuel element for a pressurized water reactor and a method for manufacturing the same
JP2814981B2 (en) Fuel assembly
JP3983493B2 (en) Zirconium-based alloy manufacturing method
WO2000036170A1 (en) Zirconium based alloy and component in a nuclear energy plant
US4169743A (en) Zirconium-base alloy nuclear fuel container and method
JPS6026650A (en) Fuel cladding pipe for nuclear reactor
JP2004238737A (en) Zirconium-based alloy and nuclear reactor structural part made of the same
CN117144264A (en) Ferrite heat-resistant alloy for light water reactor fuel assembly, manufacturing method and application

Legal Events

Date Code Title Description
AS Assignment

Owner name: COMPAGNIE EUROPEENNE DU ZIRCONIUM-CEZUS, FRANCE

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNORS:BARBERIS, PIERRE;RIZZI, JOSEPH NOEL;ROBBE, XAVIER;REEL/FRAME:017414/0309;SIGNING DATES FROM 20050613 TO 20050620

STCB Information on status: application discontinuation

Free format text: ABANDONED -- FAILURE TO RESPOND TO AN OFFICE ACTION