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 PDFInfo
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- 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
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- zirconium alloy
- zirconium
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- 229910001093 Zr alloy Inorganic materials 0.000 title claims abstract description 53
- 239000000047 product Substances 0.000 title claims abstract description 43
- 238000004519 manufacturing process Methods 0.000 title claims abstract description 40
- 239000011265 semifinished product Substances 0.000 title claims abstract description 22
- 238000000034 method Methods 0.000 title claims description 32
- 238000005242 forging Methods 0.000 claims abstract description 37
- 229910045601 alloy Inorganic materials 0.000 claims abstract description 34
- 239000000956 alloy Substances 0.000 claims abstract description 34
- 238000005266 casting Methods 0.000 claims abstract description 5
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 16
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 11
- 229910052726 zirconium Inorganic materials 0.000 claims description 11
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 10
- ATJFFYVFTNAWJD-UHFFFAOYSA-N Tin Chemical compound [Sn] ATJFFYVFTNAWJD-UHFFFAOYSA-N 0.000 claims description 10
- 239000011135 tin Substances 0.000 claims description 10
- 229910052718 tin Inorganic materials 0.000 claims description 10
- 229910052742 iron Inorganic materials 0.000 claims description 8
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 6
- 229910052804 chromium Inorganic materials 0.000 claims description 6
- 239000011651 chromium Substances 0.000 claims description 6
- 239000012535 impurity Substances 0.000 claims description 6
- 229910052758 niobium Inorganic materials 0.000 claims description 6
- 239000010955 niobium Substances 0.000 claims description 6
- GUCVJGMIXFAOAE-UHFFFAOYSA-N niobium atom Chemical compound [Nb] GUCVJGMIXFAOAE-UHFFFAOYSA-N 0.000 claims description 6
- 229910052759 nickel Inorganic materials 0.000 claims description 5
- XUIMIQQOPSSXEZ-UHFFFAOYSA-N Silicon Chemical compound [Si] XUIMIQQOPSSXEZ-UHFFFAOYSA-N 0.000 claims description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 4
- 229910052760 oxygen Inorganic materials 0.000 claims description 4
- 239000001301 oxygen Substances 0.000 claims description 4
- 229910052710 silicon Inorganic materials 0.000 claims description 4
- 239000010703 silicon Substances 0.000 claims description 4
- 239000000654 additive Substances 0.000 claims description 3
- 230000000996 additive effect Effects 0.000 claims description 3
- 229910052720 vanadium Inorganic materials 0.000 claims description 3
- LEONUFNNVUYDNQ-UHFFFAOYSA-N vanadium atom Chemical compound [V] LEONUFNNVUYDNQ-UHFFFAOYSA-N 0.000 claims description 3
- 239000003758 nuclear fuel Substances 0.000 claims description 2
- 230000008569 process Effects 0.000 description 21
- 238000010791 quenching Methods 0.000 description 16
- 230000000171 quenching effect Effects 0.000 description 16
- 239000000446 fuel Substances 0.000 description 15
- 150000004678 hydrides Chemical class 0.000 description 13
- 238000010438 heat treatment Methods 0.000 description 11
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 8
- 229910052739 hydrogen Inorganic materials 0.000 description 8
- 239000001257 hydrogen Substances 0.000 description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- 230000000712 assembly Effects 0.000 description 6
- 238000000429 assembly Methods 0.000 description 6
- 239000000203 mixture Substances 0.000 description 6
- 230000015572 biosynthetic process Effects 0.000 description 5
- 239000007795 chemical reaction product Substances 0.000 description 5
- 238000005260 corrosion Methods 0.000 description 5
- 230000007797 corrosion Effects 0.000 description 5
- 238000011282 treatment Methods 0.000 description 5
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 4
- 229910052799 carbon Inorganic materials 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 238000005204 segregation Methods 0.000 description 4
- 238000000137 annealing Methods 0.000 description 3
- 238000005097 cold rolling Methods 0.000 description 3
- 230000009931 harmful effect Effects 0.000 description 3
- 238000005098 hot rolling Methods 0.000 description 3
- 125000006850 spacer group Chemical group 0.000 description 3
- 230000000930 thermomechanical effect Effects 0.000 description 3
- 229910001257 Nb alloy Inorganic materials 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 230000009466 transformation Effects 0.000 description 2
- 230000007704 transition Effects 0.000 description 2
- 229910001297 Zn alloy Inorganic materials 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- -1 hydrides form Chemical group 0.000 description 1
- 239000013067 intermediate product Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000002459 sustained effect Effects 0.000 description 1
Images
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
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C16/00—Alloys based on zirconium
-
- 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
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.
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- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
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- 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
- 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.
- 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.
- 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.
-
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 inFIG. 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 onFIG. 1 . - The
thick slab 3 then undergoes quenching in water or humid air as shown symbolically by the arrows representing athird stage 4 of the production process. - In a fourth stage indicated by 5 in
FIG. 1 , thethick 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 theslab 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 stage 2 of forging in the beta phase (above 1000° C.) followed bystage 4 of quenching theslab 3′ from the beta phase and forging in the alpha phase at a temperature below 800° C., with asingle 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 andZircaloy 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 andZircaloy 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.
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 |
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US20060081313A1 true US20060081313A1 (en) | 2006-04-20 |
Family
ID=32524867
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
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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 |
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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)
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)
Publication number | Priority date | Publication date | Assignee | Title |
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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)
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)
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 |
-
2003
- 2003-01-13 FR FR0300316A patent/FR2849865B1/en not_active Expired - Fee Related
-
2004
- 2004-01-09 US US10/541,262 patent/US20060081313A1/en not_active Abandoned
- 2004-01-09 WO PCT/FR2004/000036 patent/WO2004072318A1/en active Application Filing
- 2004-01-09 EP EP04701028A patent/EP1585841A1/en not_active Withdrawn
- 2004-01-09 JP JP2006502091A patent/JP2006520430A/en active Pending
- 2004-01-09 KR KR1020057012999A patent/KR20050090456A/en not_active Withdrawn
- 2004-01-09 RU RU2005125715/02A patent/RU2337177C2/en not_active IP Right Cessation
- 2004-01-09 CN CNB200480002113XA patent/CN100529148C/en not_active Expired - Fee Related
Patent Citations (8)
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)
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 |
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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 |
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