US20160232991A1 - Layer protecting the surface of zirconium alloys used in nuclear reactors - Google Patents

Layer protecting the surface of zirconium alloys used in nuclear reactors Download PDF

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Publication number
US20160232991A1
US20160232991A1 US15/022,536 US201415022536A US2016232991A1 US 20160232991 A1 US20160232991 A1 US 20160232991A1 US 201415022536 A US201415022536 A US 201415022536A US 2016232991 A1 US2016232991 A1 US 2016232991A1
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United States
Prior art keywords
layer
polycrystalline diamond
zirconium alloys
carbon
diamond
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Abandoned
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US15/022,536
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English (en)
Inventor
Radek SKODA
Jan SKAROHLID
Irena KRATOCHVILOVA
Frantisek FENDRYCH
Andrew James Taylor
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CZECH TECHNICAL UNIVERSITY IN PRAGUE FACULTY OF MECHANICAL ENGINEERING DEPARTMENT OF ENERGY ENGINEERING
Czech Technical University In Prague Faculty Of M Echanical Engineering Department Of Energy Engie
Fyzikalni Ustav AV CR VVI
Original Assignee
Czech Technical University In Prague Faculty Of M Echanical Engineering Department Of Energy Engie
Fyzikalni Ustav AV CR VVI
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Application filed by Czech Technical University In Prague Faculty Of M Echanical Engineering Department Of Energy Engie, Fyzikalni Ustav AV CR VVI filed Critical Czech Technical University In Prague Faculty Of M Echanical Engineering Department Of Energy Engie
Assigned to CZECH TECHNICAL UNIVERSITY IN PRAGUE, FACULTY OF MECHANICAL ENGINEERING, DEPARTMENT OF ENERGY ENGINEERING, INSTITUTE OF PHYSICS OF THE ACADEMY OF SCIENCES OF THE CZECH REPUBLIC, V.V.I. reassignment CZECH TECHNICAL UNIVERSITY IN PRAGUE, FACULTY OF MECHANICAL ENGINEERING, DEPARTMENT OF ENERGY ENGINEERING ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: FENDRYCH, Frantisek, TAYLOR, ANDREW JAMES, SKODA, RADEK, KRATOCHVILOVA, Irena, SKAROHLID, JAN
Publication of US20160232991A1 publication Critical patent/US20160232991A1/en
Abandoned legal-status Critical Current

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    • C—CHEMISTRY; METALLURGY
    • C23—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; CHEMICAL SURFACE TREATMENT; DIFFUSION TREATMENT OF METALLIC MATERIAL; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL
    • C23C—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; SURFACE TREATMENT OF METALLIC MATERIAL BY DIFFUSION INTO THE SURFACE, BY CHEMICAL CONVERSION OR SUBSTITUTION; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL
    • C23C16/00—Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition [CVD] processes
    • C23C16/22—Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition [CVD] processes characterised by the deposition of inorganic material, other than metallic material
    • C23C16/26—Deposition of carbon only
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • C—CHEMISTRY; METALLURGY
    • C23—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; CHEMICAL SURFACE TREATMENT; DIFFUSION TREATMENT OF METALLIC MATERIAL; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL
    • C23C—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; SURFACE TREATMENT OF METALLIC MATERIAL BY DIFFUSION INTO THE SURFACE, BY CHEMICAL CONVERSION OR SUBSTITUTION; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL
    • C23C16/00—Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition [CVD] processes
    • C23C16/22—Chemical coating by decomposition of gaseous compounds, without leaving reaction products of surface material in the coating, i.e. chemical vapour deposition [CVD] processes characterised by the deposition of inorganic material, other than metallic material
    • C23C16/26—Deposition of carbon only
    • C23C16/27—Diamond only
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G21C17/0225—Chemical surface treatment, e.g. corrosion
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34—Spacer grids
    • 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

Definitions

  • the presented solution deals with the protection of zirconium alloys surface against undesirable changes and processes in light-water and heavy-water nuclear reactors.
  • zirconium alloys are present in all commercially operated power producing light-water (PWR, BWR, VVER) and heavy-water (CANDU) nuclear reactors.
  • PWR, BWR, VVER light-water
  • CANDU heavy-water
  • Zirconium alloys are used as a material for nuclear fuel rods and also for other structural elements in fuel assemblies and the core of nuclear reactors, such as spacer grids or complete pressure channels.
  • the reason for their use is mainly the low parasitic absorption of neutrons and high resistance against radiation damage.
  • Zirconium alloys also feature very good mechanical properties and corrosion stability, which are maintained even during long-term exposure to extreme conditions produced in nuclear reactors, especially high neutron flux, high pressure and temperature.
  • zirconium alloys have natural thin passivated layer of zirconium dioxide with a thickness of about 3-5 ⁇ m.
  • This thin oxide layer protects the alloy itself from further oxidation.
  • the oxidation rate is limited by the rate of oxygen diffusion through the passivated layer of ZrO2.
  • the oxide layer thickness is about 20 ⁇ m, depending on the reactor type, the type of alloy, the quality of water during operation and the burnout degree.
  • Temperature is the most important factors affecting High-temperature corrosion, because reaction kinetics increases with increasing temperature. Other influencing factors are: exposure time of hot alloy in air, which leads to the formation of zirconium nitride, and then in case of reaction with steam leads to intensive release heat, the initial oxidation of the zirconium alloy, which is directly proportional to the residence time in the reactor, the presence of other materials in the melting core and more.
  • the weaknesses mentioned above are removed by coating zirconium alloys used in nuclear reactors with a protective layer formed by homogenous polycrystalline diamond layer prepared by the chemical vapor deposition method.
  • This diamond layer is 100 nm to 50 ⁇ m thick where the size of crystalline is ranging from 10 nm to 500 nm.
  • the maximum content of non-diamond carbon is 25 mol %
  • total content of non-carbon impurities is up to a maximum of 0.5 mol %
  • RMS surface roughness of the polycrystalline diamond layer has a value less than 40 nm and thermal conductivity of the layer ranges from 1000 to 1900 W ⁇ m ⁇ 1 ⁇ K ⁇ 1 .
  • the polycrystalline diamond layer protects the surface of the zirconium alloy against high-temperature corrosion, which involves peeling the protective oxide layer and subsequently mechanical failure of the entire system.
  • the layer of polycrystalline diamond will prevent also the reaction between zirconium and water steam. During such reaction water steam molecules dissociate and subsequently zirconium oxide and hydrogen are formed whilst huge amounts of heat are generated.
  • the protective layer therefore prevents the formation of hydrogen, which being an explosive gas is a serious hazard in the case of a severe accident. Simultaneously it also prevents the generation of increased amounts of reaction heat that would further complicate active zone cooling and intensify, further, the process of zirconium alloy oxidation.
  • FIG. 1 and FIG. 2 showing the Raman spectrum of the homogenous polycrystalline diamond layer covering the sample of the fuel element made of zirconium alloy both in the basic condition and after simulation of standard as well as emergency conditions of the nuclear reactor.
  • FIG. 1 peaks of Raman spectra show vibrational states of various phases of carbon protective layer.
  • FIG. 2 shows that after ion implantation, simulating material interaction with particles in a nuclear reactor, the polycrystalline diamond layer underwent partial graphitization but the diamond crystalline phase in the layer was still present. After simulation at accident conditions, i.e. exposure to hot water steam, a phase change in the protective layer occurred, during which the crystalline diamond transformed into a mixture of graphite, graphene and amorphous carbon.
  • the proposed solution and the subject of this patent is the protection of the surface of zirconium alloys used as materials in nuclear reactors by polycrystalline diamond layers.
  • Diamond features high thermal conductivity and stability, low chemical reactivity, it does not degrade over time and has a suitable effective cross-section for interaction with neutrons.
  • the surface of elements made of zirconium alloys are coated with homogenous polycrystalline diamond layers prepared by chemical vapor deposition method, abbreviated as CVD, with typical columnar nature of diamond crystallites.
  • the CVD method means that diamond is prepared by decomposition of a mixture of methane (or other carbon containing species) and at pressures from 0.01 mbar to 100 mbar and at substrate temperatures of 250° C. to 1000° C.
  • Polycrystalline diamond layers suitable for the protection of zirconium alloys surface is 100 nm to 50 ⁇ m thick and with crystalline cores in the layer ranges from 10 nm to 500 nm in size. From the chemical composition point of view the layer can be specified based on the maximum content of non-diamond carbon, which is a maximum 25 mol %, and by the total content of non-diamond impurities with a maximum value of up to 0.5 mol %. Surface roughness of the polycrystalline diamond layer must not exceed the RMS roughness value of 40 nm. Thermal conductivity of the layer ranges from 1000 to 1900 W ⁇ m ⁇ 1 ⁇ K ⁇ 1 .
  • Crystalline diamond has a strong and rigid isotropic structure due to its cubic crystal symmetry—carbon atoms are bound by strong covalent bonds. On the contrary, carbon atoms in graphite are bound by different ⁇ and ⁇ bonds in the hexagonal crystalline system. In this specific configuration, one electron is weakly bounded and thus contributes to a significantly higher electrical conductivity of graphite compared to diamond. Stable planar structures of graphite are mutually bonded by Van der Waals forces, thereby forming the soft, malleable and also resistant material.
  • the polycrystalline diamond layer Under standard operation conditions in nuclear reactors the polycrystalline diamond layer will maintain its original properties and will participate both in dissipation of heat released during the reactor's operating mode, and also will protect the coated surface against undesirable chemical reactions and changes of the structure composition related to diffusion of the hydrogen atoms from dissociated molecules of water into the zirconium alloy. After long-term interaction with elementary particles released from the nuclear reactions the polycrystalline diamond layer shows partial graphitization and amorphization but the diamond crystalline phase is still present in the layer. Polycrystalline diamond layer will further limit the undesirable high-temperature chemical reactivity of the zirconium alloys surface and therefore also the high-temperature dissociation of water steam molecules and subsequent formation of the zirconium oxide and explosive hydrogen.
  • the layer will benefit from the mixed nature of the protective carbon layer, which besides crystalline diamond cores with sp 3 of hybridized carbon contains also flexible amorphous phase sp 2 from hybridized carbon capable of good adaptation to the volume changes/expansion of the metal substrate without disrupting the protective layer integrity.
  • the protective polycrystalline diamond layer undergoes a phase change. Crystalline diamond transforms into a mixture of crystalline graphite, graphene and amorphous carbon. Non-diamond carbon material, or its selected components feature a high melting temperature of 3642° C.
  • the process of the crystalline diamond thermal transformation to graphite, graphene and non-crystalline carbon consumes part of the energy from the environment, thus also at least slightly lowering its temperature.
  • This protection, carbon-containing layer further worsen the conditions for the high temperature degeneration of the surface, including the paSsivated layer, also any quenching of zirconium alloy and further reduces the probability of explosion of hydrogen.
  • FIG. 1 and FIG. 2 are examples showing the practical impact of the use of protective homogeneous polycrystalline diamond layer on zirconium samples.
  • Raman spectra of the sample of the fuel cell made from a zirconium alloy, homogeneously coated by 300 nm thick polycrystalline diamond film by vapor is deposition is shown in FIG. 1 . All the Raman spectra were measured at different locations on the surface to prove the regularity of the sample state. Raman peak positions in spectra were same at different locations on the sample surface.
  • the vibration peak at 1332 cm ⁇ 1 corresponds to the sp 3 hybridized carbon, that means the diamond phase in layer. Vibrations in the range of 1450-1650 cm ⁇ 1 correspond to the sp 2 hybridized carbon, thus non-diamond phase represented in the polycrystalline diamond layer.
  • FIG. 2 shows the Raman spectra of a homogeneous polycrystalline diamond layer covering a portion of the fuel cell of the zirconium alloy in a basic condition, after ion implantation, and heated in a steam environment at a temperature of 1100-1200° C.
  • the vibration peak at 1332 cm ⁇ 1 corresponds to the sp 3 hybridized carbon, thus the diamond phase of carbon, the vibration peak at 1355 cm ⁇ 1 to the crystalline graphite, vibrations in the range of 1450 to 1650 cm ⁇ 1 to the sp 2 hybridized carbon, thus non-diamond carbon phase
  • the Raman spectrum line of the sample coated with the polycrystalline diamond layer is shown in FIG. 2 by the full line.
  • Dashed line shows the spectrum of the sample coated with the polycrystalline diamond layer after ion implantation simulating the load of material by interaction with fundamental particles in a nuclear reactor. Ion implantation causes partial graphitization of the polycrystalline diamond layer but the diamond crystalline phase remains still present in the layer.
  • Dotted line shows the Raman spectrum of the sample coated with the polycrystalline diamond layer after simulation of accident conditions by steam oxidation when the phase change of the crystalline diamond in the protective layer occurs and the crystalline diamond transforms into the mixture of graphite, graphene and amorphous carbon.
  • Crystalline diamond has transformed into a mixture of graphite, graphene and amorphous carbon.
  • thermally transformed carbon layer comprises a mixtures of carbon, oxygen and atoms of substrate.
  • the newly composed layer thus absorbed atoms from surroundings and separated zirconium alloy surface from the surrounding environment so that its status under the protective layer from the base material Zr alloys atomic composition differed minimally.
  • the above mentioned protection of zirconium alloys surfaces by homogenous polycrystalline diamond layers may be applied to a wide range of functional elements for nuclear reactors, such as fuel rod elements. This involves, in particular, parts of commercially operated power producing light-water reactors PWR, BWR, WER and heavy-water reactors CANDU.
  • the described protective layer significantly increases such reactors' operation safety.

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Metallurgy (AREA)
  • Inorganic Chemistry (AREA)
  • General Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Manufacturing & Machinery (AREA)
  • Chemical Vapour Deposition (AREA)
  • Carbon And Carbon Compounds (AREA)
US15/022,536 2013-09-20 2014-09-16 Layer protecting the surface of zirconium alloys used in nuclear reactors Abandoned US20160232991A1 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
CZ2013-727A CZ2013727A3 (cs) 2013-09-20 2013-09-20 Vrstva, chránící povrch zirkoniových slitin užívaných v jaderných reaktorech
CZPV2013-727 2013-09-20
PCT/CZ2014/000101 WO2015039636A1 (en) 2013-09-20 2014-09-16 Layer protecting the surface of zirconium alloys used in nuclear reactors

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EP (1) EP3047046B1 (cs)
JP (1) JP2016538528A (cs)
KR (1) KR20160058176A (cs)
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ES (1) ES2831402T3 (cs)
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Cited By (4)

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US20150131768A1 (en) * 2013-11-13 2015-05-14 Areva Np Inc. Nuclear fuel rod cladding including a metal nanomaterial layer
US20180286524A1 (en) * 2017-03-31 2018-10-04 Westinghouse Electric Company Llc Spacer Grid Using Tubular Cells With Mixing Vanes
CN112011783A (zh) * 2020-09-03 2020-12-01 太原理工大学 锆合金表面氧化锆催化石墨烯生长的低温化学气相沉积法
CN117305805A (zh) * 2023-09-27 2023-12-29 上海交通大学 基于纳米金刚石涂层的核燃料包壳改性方法

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CZ307396B6 (cs) * 2016-05-10 2018-07-25 ÄŚeskĂ© vysokĂ© uÄŤenĂ­ technickĂ© v Praze, Fakulta strojnĂ­, Ăšstav energetiky Povlak zirkonového pokrytí jaderného paliva
CZ309725B6 (cs) * 2016-06-24 2023-08-23 České vysoké učení technické v Praze Palivové proutky jaderného paliva
EP3717405A4 (en) 2017-11-28 2021-12-15 Atomic Energy of Canada Limited/ Énergie Atomique du Canada Limitée SINGLE WALL CARBON NANOTUBES BASED SLUDGE FOR IMPROVED NUCLEAR FUEL CLADDING AND ITS MANUFACTURING PROCESS
CZ308454B6 (cs) * 2019-05-28 2020-08-26 Fyzikální Ústav Av Čr, V. V. I. Povlak vhodný pro ochranu vnějšího povrchu pokrytí jaderného paliva, použití povlaku, způsob výroby povlaku a jaderné palivo
US20230368931A1 (en) * 2022-05-10 2023-11-16 Westinghouse Electric Company Llc Fuel cladding covered by a mesh

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Publication number Priority date Publication date Assignee Title
US20150131768A1 (en) * 2013-11-13 2015-05-14 Areva Np Inc. Nuclear fuel rod cladding including a metal nanomaterial layer
US10102930B2 (en) * 2013-11-13 2018-10-16 Framatome Inc. Nuclear fuel rod cladding including a metal nanomaterial layer
US20180286524A1 (en) * 2017-03-31 2018-10-04 Westinghouse Electric Company Llc Spacer Grid Using Tubular Cells With Mixing Vanes
US10818402B2 (en) * 2017-03-31 2020-10-27 Westinghouse Electric Company Llc Spacer grid using tubular cells with mixing vanes
US11942230B2 (en) 2017-03-31 2024-03-26 Westinghouse Electric Company Llc Spacer grid using tubular cells
CN112011783A (zh) * 2020-09-03 2020-12-01 太原理工大学 锆合金表面氧化锆催化石墨烯生长的低温化学气相沉积法
CN117305805A (zh) * 2023-09-27 2023-12-29 上海交通大学 基于纳米金刚石涂层的核燃料包壳改性方法

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CZ305059B6 (cs) 2015-04-15
EP3047046B1 (en) 2020-08-19
EP3047046A1 (en) 2016-07-27
US20190080806A1 (en) 2019-03-14
CZ2013727A3 (cs) 2015-04-15
ES2831402T3 (es) 2021-06-08
KR20160058176A (ko) 2016-05-24
JP2016538528A (ja) 2016-12-08
WO2015039636A1 (en) 2015-03-26
US10916352B2 (en) 2021-02-09

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