CN103060726A - Zr61.5Cu21.5Fe5Al12 bulk amorphous alloy resisting Ar ion and proton irradiation, preparation method and application thereof - Google Patents

Zr61.5Cu21.5Fe5Al12 bulk amorphous alloy resisting Ar ion and proton irradiation, preparation method and application thereof Download PDF

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CN103060726A
CN103060726A CN201210515028XA CN201210515028A CN103060726A CN 103060726 A CN103060726 A CN 103060726A CN 201210515028X A CN201210515028X A CN 201210515028XA CN 201210515028 A CN201210515028 A CN 201210515028A CN 103060726 A CN103060726 A CN 103060726A
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杨滨
罗文东
王西涛
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University of Science and Technology Beijing USTB
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    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Abstract

The invention relates to an amorphous alloy, especially to a Zr61.5Cu21.5Fe5Al12 bulk amorphous alloy resisting Ar ion and proton irradiation, a preparation method and an application thereof. The alloy comprises the following chemical components, by atom percent: Zr61.5Cu21.5Fe5Al12. The bulk amorphous alloy is beneficial for saving strategic material Zr, the Zr-Cu-Fe-Al amorphous alloy (containing less than 65 atomic % of Zr) with relatively low Zr content is used to partially substitute widely-used high Zr alloy for fuel assembly in present, thereby being of great significance of saving scarce strategic material Zr. Besides Zr, Cu, Fe and Al in the alloy is rich in sources and green. The preparation method provided by the invention is easy to control and relatively low in comprehensive cost; and the Zr-based amorphous alloy has good performances of resisting Ar ion, proton irradiation and H2SO4, and is expected to be alternative materials of fuel cladding materials of nuclear power stations.

Description

The Zr of a kind of ion of anti-Ar and proton irradiation 61.5Cu 21.5Fe 5Al 12Bulk amorphous alloys, preparation method and application thereof
Technical field
The present invention relates to amorphous alloy, relate in particular to the Zr of a kind of ion of anti-Ar and proton irradiation 61.5Cu 21.5Fe 5Al 12Bulk amorphous alloys, preparation method and application thereof.
Background technology
As everyone knows, the q﹠r of nuclear material is depended in the security of Nuclear power plants to a great extent.For this reason, nuclear power developed country has all dropped into research and development and the performance study that a large amount of man power and materials carries out the nuclear power critical material in the world.Based on protecting the intellectual property and accounting for commercioganic purpose, the countries such as France, Russia, America ﹠ Canada have all formed nuclear material standard specifications separately, and by patented technology the intellecture property of this country's research and development product are protected.For technology barriers and the restriction that breaks through nuclear material, grasp the core technology of nuclear material production and manufacturing, be badly in need of the Nuclear power plants key structure material that research and development have China's independent intellectual property right.
Pressurized-water reactor nuclear power plant is divided into nuclear island and conventional island two portions, and wherein nuclear island is the core of Nuclear power plants, and fuel assembly is the core of nuclear reactor.Fuel assembly is the operating running stores of Nuclear power plants.The Zr alloy cladding material that in the past was used for fuel assembly, each refulling cycle (12 or 18 months), need to change 1/3 assembly, consume about 10 tons of zirconium alloy, this be because, zirconium alloy is subjected to neutron irradiation in reactor, intensity can raise, material can become fragile; Secondly, because-Zr genus hexagonal structure metal, the irradiation growth that the meeting generation is shunk along expansion and the c direction of a direction under the effect of irradiation produces the phenomenons such as creep and internal stress, makes its over-all properties variation; Moreover, when the Zr alloy is on active service, except bearing neutron irradiation, also bearing the corrosion of High Temperature High Pressure water quality environment in nuclear reactor, cause alloy corrosion speed to raise even cracking.In order to reduce Fuel cycle, improve reactor power, to prolong the refulling cycle, development Zr alloy cladding material is paid much attention in countries in the world.For example, the nineties in 20th century, France successfully develops the M5 alloy.In recent years, American R ﹠ D goes out the ZIRLO alloy.In addition, N18 and the N36 alloy of the PCA alloy of the HANA alloy of the NDA alloy of the E635 alloy of Russia's development, Japan's development, Korea S's development, Germany's development and China's development all have good over-all properties.But it is to be noted, China only possesses the throughput for Small nuclear power plant first-generation Zr alloy cladding material (Zr-4 alloy) at present, not yet grasps the production technology that large-scale advanced nuclear reactor high burnup (burnup is greater than 60GWd/tU) involucrum is used the Zr alloy industry.So far, the whole dependence on import of China's used in nuclear power station high burnup Zr alloy cladding material.Based on protecting the intellectual property and accounting for commercioganic purpose; the countries such as France, Russia and the U.S. have all formed nuclear material standard specifications separately, and by patented technology (accounting for more than 80% of total amount in the patent aspect the zirconium alloy Composition Design of China's application abroad) intellecture property of this country's research and development product are protected.In fact, even if at present various countries pay much attention to the Zr alloy fuel assembly of development, also there are many difficult points at aspects such as the production technique of ingot casting technology of preparing, cladding tubes and texture control techniquess.For example, in utilizing vacuum consumable electrode arc furnace melting Zr-Sn-Nb alloy process, owing to factors such as the velocity of diffusion of Nb are slow, and the fusing point difference of Sn and Zr and Nb is large, ensure that the accurate control of composition and the homogeneity of large ingot casting is difficult.And for example, in order to obtain the Zr-Sn-Nb alloy cladding pipe of high dimensional accuracy and good texture, need to be under the prerequisite of machining at low temperature technique, the thermal treatment process such as optimizing uniform annealing, employing β quenching, the size of control precipitated phase and distribution.Simultaneously, general working rate and pass reduction between control annealing with the texture of control cladding tubes tubing, and then are finally controlled the orientation of hydride.Therefore, the s Nuclear Plant can material of development of new, should face on the basis of subject matter in analysis Zr alloy fuel component application, in conjunction with our existing achievement in research, propose the alloy designs new departure with independent intellectual property right.
In recent years, irradiation causes Materials science worker's concern to the impact of non-crystaline amorphous metal tissue and mechanics, corrosive nature.Non-crystaline amorphous metal belongs to unidirectional amorphous structure, does not have the textural defect such as crystal boundary, dislocation and fault, does not also have component segregation and Second Phase Precipitation, and the homogeneity of this microstructure and composition makes it possess the prerequisite of good anti-irradiation and local corrosive power.Simultaneously, the activity of amorphous alloy self is very high, can form rapidly from the teeth outwards uniform passive film, therefore has good erosion resistance.On the other hand, because the bonding between the zirconium-base amorphous alloy Atom is better than the bonding between zirconium base crystal alloy Atom, and does not exist the phenomenon that produces slippage owing to the motion of dislocation in the zirconium-base amorphous alloy, so its good mechanical performance.The crystallization temperature of most of Zr base noncrystal alloy is higher than 700K, is expected to keep in 330 ℃ of high-temperature water media of reactor core pressure vessel tissue stable.Simultaneously, pressurized-water reactor nuclear power plant fuel assembly (comprise involucrum tubing, end plug with bar, location grid with piece of tape etc.) is of a size of several or tens millimeters mostly, can adopt current at present Zr base block amorphous alloy technology of preparing to be shaped fully.Thereby the Zr base noncrystal alloy is expected to become the equivalent material of fuel assembly for nuclear reactor Zr base crystal alloy can material.Present patent application is on the basis of existing nuclear power fuel assembly material and bulk amorphous alloys research, proposition is applied to the fuel assembly for nuclear reactor can material with the Zr base noncrystal alloy, for the practical application of researching and developing novel s Nuclear Plant can material, expansion non-crystaline amorphous metal provides a brand-new path.
Summary of the invention
The purpose of this invention is to provide a kind of Zr 61.5Cu 21.5Fe 5Al 12Amorphous alloy, preparation method and the application aspect the s Nuclear Plant can material thereof, it has performance and the corrosion resistance nature of the good ion of anti-Ar and proton irradiation.
The zirconium-base amorphous alloy owner with strong glass forming ability of report will comprise Zr-Al-Ni-Cu and Zr-Cu-Fe-Al system at present, and their critical size all can reach centimetre-sized.The result that studies for a long period of time shows that Ni can increase the hydrogen－sucking amount of zirconium in zirconium alloy, cause hydrogen embrittlement.In conjunction with existing amorphous component design theory and experience, the final selection of present patent application has the Zr-Al-Fe-Cu Al-Cu-Zn block amorphous alloy of high glass forming ability and low thermal neutron absorption cross section, investigates the performance of its ion of anti-Ar and proton irradiation.
For achieving the above object, the present invention adopts following technical scheme.
A kind of ion of anti-Ar and proton irradiation Zr-Cu-Fe-Al bulk amorphous alloys, this alloying constituent is in atomic percent, and its chemical constitution is Zr 61.5Cu 21.5Fe 5Al 12
The preparation method of above-mentioned Zr-Cu-Fe-Al bulk amorphous alloys comprises following preparation process:
The preparation of a, mother alloy: take its chemical constitution of atomic percent as Zr 61.5Cu 21.5Fe 5Al 12Prepare burden, and Zr, Cu, Fe, Al are high-purity material; Adopt vacuum arc fumace, water jacketed copper crucible melting, preparation Zr 61.5Cu 21.5Fe 5Al 12Mother alloy;
The preparation of b, non-crystaline amorphous metal: utilize vacuum arc fumace with the master alloy ingot remelting among the step a, melt rear employing suction casting method fully until it Zr-Cu-Fe-Al alloy is sucked in the water cooled copper mould fast, make Zr 61.5Cu 21.5Fe 5Al 12Non-crystaline amorphous metal.
This preparation method's preferred version is that it is that 99.9wt%, Cu are that 99.98wt%, Fe are that 99.9wt%, Al are 99.99wt% that described raw-material purity is higher than respectively following parameters Zr.
This preparation method's preferred version is that the described melting of step a is alloy cast ingot melt back 4 times.
This preparation method's preferred version is that the described suction casting method of step b is that whole furnace chamber is evacuated to 1 * 10 -3Pa after alloy material melts fully, is communicated with the copper mold cavity with vacuum pump, utilize the pressure difference of furnace chamber and copper mold cavity that alloy melt is sucked water cooled copper mould fast, obtains bar-shaped cast ingot.
This preparation method's preferred version is, the described melting of step a is being carried out in the high-purity argon gas atmosphere of superfusion titanium oxygen consumption, and its purity is 99.999%.
The application of above-mentioned Zr-Cu-Fe-Al bulk amorphous alloys, the application of this non-crystaline amorphous metal aspect s Nuclear Plant.
The preferred version that Zr-Cu-Fe-Al bulk amorphous alloys of the present invention is used, the application of described non-crystaline amorphous metal aspect the Nuclear power plants can material.
For detecting the Zr of preparation 61.5Cu 21.5Fe 5Al 12The feasibility that non-crystaline amorphous metal is used aspect the fuel for nuclear power plant can material needs to carry out performance test to it, but directly in heap the neutron irradiation damage one of research material be that the irradiation test time is long, the 2nd, somewhat expensive.The present invention adopts following laboratory facilities and parameter: (1) selects rare gas element Ar ion as irradiate ion, with the detrimentally affect of avoiding ion and matrix element generation chemical reaction to bring.For selecting suitable ion energy and dosage, neutron irradiation adopts SRIM(the Stopping and Range of Ions in Matter to the level of damage of zirconium alloy in the simulation nuclear reactor) program carried out analog calculation.Calculation result shows, selects Ar ion, the dosage of 300keV to be respectively 3 * 10 15, 1 * 10 16With 3 * 10 16/ cm 2Carry out irradiation, the mean vacancy rate that the horizontal dpa of the surface damage that obtains, ion bombardment mean depth and ion bombardment produce has reached the level of damage of neutron irradiation zirconium alloy in the nuclear reactor; (2) select penetration depth large (with the proton of the several MeV of energy, penetration depth can reach tens microns), fluence rate (can reach 10 greatly -4Dpa/s, the neutron irradiation fluence rate is 10 in the heap -7Dpa/s), the proton that the radioactivation degree is little carries out irradiation.Irradiation dose is respectively 1 * 10 13/ cm 2, 1 * 10 14/ cm 2With 1 * 10 15/ cm 2, beam current density is 100 ~ 200nA/s.
Beneficial effect of the present invention is: (1) is conducive to save strategic materials Zr.The Zr amount that contains of present commercial Zr-Sn, Zr-Nb and Zr-Sn-Nb alloy system is all up to more than the 97 atom %.As previously mentioned, Zr alloy fuel assembly is the operating running stores of Nuclear power plants, and each refulling cycle (12 or 18 months), 1/3 fuel assembly needs to change.Million kilowatt nuclear power unit will consume about 400 tons of zirconium alloy claddings in whole life cycle in 40 years, and total value is above 1,000,000,000 yuans.According to incompletely statistics, nearly 190 tons of the Year's consumption of the annual zirconium alloy cladding of China estimated that annual requirement will reach 390 tons in 2025, and the overall market is worth about 12～1,300,000,000 yuan.Substitute existing widely used fuel assembly with high Zr alloy with the relatively low Zr-Cu-Fe-Al non-crystaline amorphous metal of Zr content (contain the Zr amount and be lower than 65 atom %) part, significant to saving strategic materials Zr in short supply.(2) except Zr, the Cu in the alloy, Fe, abundant, the environmental protection in Al source, preparation process of the present invention is controlled easily, and comprehensive cost is lower.(3) Zr base amorphous alloy of the present invention has the good ion of anti-Ar, proton irradiation and H 2SO 4Performance, be expected to become the equivalent material of fuel for nuclear power plant can material.
Description of drawings
Fig. 1 is Zr 60+xCu 23-xFe 5Al 12(atom %, x=1.5,3,4.5) are the XRD spectrum of alloy, as can be seen from the figure only have Zr 61.5Cu 21.5Fe 5Al 12Alloy demonstrates the full amorphous structure without any the Bragg peak.
Fig. 2 is Zr 61.5Cu 21.5Fe 5Al 12The high-resolution-ration transmission electric-lens of alloy sample (HRTEM) image and corresponding SAD diffraction pattern further show the Zr of preparation 61.5Cu 21.5Fe 5Al 12Alloy is full amorphous structure.
Fig. 3 is Zr 61.5Cu 21.5Fe 5Al 12The differential thermal analysis of non-crystaline amorphous metal (DSC) curve can be found out the glass transformation temperature (T of this non-crystaline amorphous metal from curve g) be 675K, crystallization temperature (T x) be 765K, Δ T xBe 90K.
Fig. 4 is Zr 61.5Cu 21.5Fe 5Al 12The Kissinger figure of non-crystaline amorphous metal.Obtain Zr by rate of curve 61.5Cu 21.5Fe 5Al 12The glass transition Apparent activation energy E of non-crystaline amorphous metal gBe 255.2kJ/mol, the Apparent activation energy E of beginning crystallization xBe 274.9kJ/mol, crystallization peak value Apparent activation energy E pBe 285.7kJ/mol.Show Zr 61.5Cu 21.5Fe 5Al 12Non-crystaline amorphous metal has good anti-crystallization ability and high thermostability.
Fig. 5 is that the Ar ion of 300keV is respectively with 3 * 10 15, 1 * 10 16With 3 * 10 16/ cm 2Dosage irradiation Zr 61.5Cu 21.5Fe 5Al 12XRD spectrum behind the non-crystaline amorphous metal sample.Can find out that therefrom obvious crystallization peak does not appear in the XRD of sample behind the ion irradiation, Zr behind the irradiation is described 61.5Cu 21.5Fe 5Al 12Alloy still keeps amorphous structure.
Fig. 6 is Zr 61.5Cu 21.5Fe 5Al 12The XRD figure of non-crystaline amorphous metal before and after the 2MeV proton irradiation.Can find out, under the proton irradiation dosage that increases progressively successively, obvious crystallization peak not occur, show that the 2MeV proton irradiation does not obviously change Zr yet 61.5Cu 21.5Fe 5Al 12The amorphous structure of non-crystaline amorphous metal.
Fig. 7 is Zr 61.5Cu 21.5Fe 5Al 12Electrokinetic potential polarization curve (0.5mol/L H under non-crystaline amorphous metal and the pure Zr sample room temperature 2SO 4Solution, surface sweeping speed are 1mv/s).As seen, Zr 61.5Cu 21.5Fe 5Al 12Non-crystaline amorphous metal has larger corrosion potential than it pure Zr, shows Zr 61.5Cu 21.5Fe 5Al 12The anti-H of non-crystaline amorphous metal 2SO 4The corrosive nature of solution is better than pure Zr.
Embodiment
Embodiment 1: preparation Zr-Cu-Fe-Al is alloy
The chemical constitution of this zirconium base alloy is counted Zr with atomic percent 60+xCu 23-xFe 5Al 12, wherein X=1.5 prepares burden with following formula, and wherein, Zr purity reaches 99.9wt%, Cu purity and reaches that 99.98wt%, Fe purity reach 99.9wt%, Al purity reaches 99.99wt%.Adopting vacuum tightness is 1 * 10 -3Electric arc furnace/water jacketed copper crucible of Pa prepares above-mentioned mother alloy; And melting atmosphere is the high-purity argon gas (99.999%) through superfusion titanium oxygen consumption, and the equal melt back of each alloy pig 4 times is to guarantee that alloying constituent is even.
Utilize vacuum arc fumace with above-mentioned master alloy ingot remelting, its vacuum tightness is set as 1 * 10 -3Pa.Melt rear employing suction casting method fully with Zr until it 61.5Cu 21.5Fe 5Al 12Alloy sucks in the water cooled copper mould fast, prepares the non-crystaline amorphous metal that diameter is 3mm, and described suction casting method is that whole furnace chamber is evacuated to 1 * 10 -3Pa after alloy material melts fully, is communicated with the copper mold cavity with vacuum pump, utilize the pressure difference of furnace chamber and copper mold cavity that alloy melt is sucked water cooled copper mould fast, obtains bar-shaped cast ingot.As depicted in figs. 1 and 2, XRD diffraction and high-resolution-ration transmission electric-lens (HRTEM) analytical results shows Zr 61.5Cu 21.5Fe 5Al 12Sample is full amorphous structure.
Embodiment 2
Be the Zr of 3mm with the diameter of above-mentioned preparation 61.5Cu 21.5Fe 5Al 12The amorphous barred body cuts into the disk of the thick 0.6 ~ 1mm of being, through sand papering, surface finish, acetone and raw spirit clean, the washed with de-ionized water post-drying preserves.Be respectively 3 * 10 with 300keV, dosage 15, 1 * 10 16With 3 * 10 16/ cm 2Ar ion pair circular disc test specimen surface carry out ion bombardment, beam current density is respectively 0.354,0.354 and 0.531 μ A/cm 2As shown in Figure 5, the XRD diffraction result of sample shows Zr behind the irradiation 61.5Cu 21.5Fe 5Al 12Alloy still keeps full amorphous structure.
Embodiment 3
Be the Zr of 3mm with the diameter of above-mentioned preparation 61.5Cu 21.5Fe 5Al 12The amorphous barred body cuts into the disk of the thick 0.6 ~ 1mm of being, through sand papering, surface finish, acetone and raw spirit clean, the washed with de-ionized water post-drying preserves.Be 2MeV with energy, dosage is respectively 1 * 10 13/ cm 2, 1 * 10 14/ cm 2With 1 * 10 15/ cm 2, beam current density is 100 ~ 200nA/cm 2Proton carries out proton bombardment to the circular disc test specimen surface.As shown in Figure 6, the XRD diffraction result of sample shows Zr behind the irradiation 61.5Cu 21.5Fe 5Al 12Alloy still keeps full amorphous structure.
Embodiment 4
Be the Zr of 3mm with the diameter of above-mentioned preparation 61.5Cu 21.5Fe 5Al 12Amorphous barred body and pure Zr sample are at the H of 0.5mol/L 2SO 4Test electrokinetic potential polarization curve in the solution, the electrokinetic potential interval is-1 ~ 2.2V, scanning speed is 1mv/s.As shown in Figure 7, Zr 61.5Cu 21.5Fe 5Al 12Non-crystaline amorphous metal has larger corrosion potential than it pure Zr.

Claims (8)

1. the ion of anti-Ar and proton irradiation Zr-Cu-Fe-Al bulk amorphous alloys, it is characterized in that: this alloying constituent is in atomic percent, and its chemical constitution is Zr 61.5Cu 21.5Fe 5Al 12
2. the preparation method of described Zr-Cu-Fe-Al bulk amorphous alloys according to claim 1 is characterized in that, comprises following preparation process:
The preparation of a, mother alloy: take its chemical constitution of atomic percent as Zr 61.5Cu 21.5Fe 5Al 12Prepare burden, and Zr, Cu, Fe, Al are high-purity material; Adopt vacuum arc fumace, water jacketed copper crucible melting, preparation Zr 61.5Cu 21.5Fe 5Al 12Mother alloy;
The preparation of b, non-crystaline amorphous metal: utilize vacuum arc fumace with the master alloy ingot remelting among the step a, melt rear employing suction casting method fully until it Zr-Cu-Fe-Al alloy is sucked in the water cooled copper mould fast, make Zr 61.5Cu 21.5Fe 5Al 12Non-crystaline amorphous metal.
3. the preparation method of Zr-Cu-Fe-Al bulk amorphous alloys according to claim 2, it is characterized in that: it is that 99.9wt%, Cu are that 99.98wt%, Fe are that 99.9wt%, Al are 99.99wt% that described raw-material purity is higher than respectively following parameters Zr.
4. the preparation method of Zr-Cu-Fe-Al bulk amorphous alloys according to claim 2, it is characterized in that: the described melting of step a is alloy cast ingot melt back 4 times.
5. the preparation method of Zr-Cu-Fe-Al bulk amorphous alloys according to claim 2, it is characterized in that: the described suction casting method of step b is that whole furnace chamber is evacuated to 1 * 10 -3Pa after alloy material melts fully, is communicated with the copper mold cavity with vacuum pump, utilize the pressure difference of furnace chamber and copper mold cavity that alloy melt is sucked water cooled copper mould fast, obtains bar-shaped cast ingot.
6. the preparation method of Zr-Cu-Fe-Al bulk amorphous alloys according to claim 2 is characterized in that, the described melting of step a is being carried out in the high-purity argon gas atmosphere of superfusion titanium oxygen consumption, and its purity is 99.999%.
7. the application of each described Zr-Cu-Fe-Al bulk amorphous alloys is characterized in that according to claim 1～6, the application of described non-crystaline amorphous metal aspect s Nuclear Plant.
8. the according to claim 7 application of described Zr-Cu-Fe-Al bulk amorphous alloys is characterized in that, the application of described non-crystaline amorphous metal aspect the Nuclear power plants can material.
CN201210515028XA 2012-12-04 2012-12-04 Zr61.5Cu21.5Fe5Al12 bulk amorphous alloy resisting Ar ion and proton irradiation, preparation method and application thereof Pending CN103060726A (en)

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Cited By (3)

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CN103556085A (en) * 2013-10-30 2014-02-05 北京科技大学 Zr-Al-Cu-Fe-Nb block amorphous alloy and preparation method thereof
CN104178716A (en) * 2014-07-31 2014-12-03 郑州大学 Optimizing technology for improving corrosion-resisting property of ZrCuNiAlTi block metal glass
EP3477660A1 (en) 2017-10-26 2019-05-01 Westinghouse Electric Sweden AB A cladding tube, and a method of manufacturing a cladding tube

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Publication number Priority date Publication date Assignee Title
CN103556085A (en) * 2013-10-30 2014-02-05 北京科技大学 Zr-Al-Cu-Fe-Nb block amorphous alloy and preparation method thereof
CN103556085B (en) * 2013-10-30 2016-05-25 北京科技大学 Zr-Al-Cu-Fe-Nb block amorphous alloy and preparation method
CN104178716A (en) * 2014-07-31 2014-12-03 郑州大学 Optimizing technology for improving corrosion-resisting property of ZrCuNiAlTi block metal glass
EP3477660A1 (en) 2017-10-26 2019-05-01 Westinghouse Electric Sweden AB A cladding tube, and a method of manufacturing a cladding tube
WO2019081338A1 (en) 2017-10-26 2019-05-02 Westinghouse Electric Sweden Ab A cladding tube, and a method of manufacturing a cladding tube

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