CN111636082A - Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element - Google Patents

Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element Download PDF

Info

Publication number
CN111636082A
CN111636082A CN202010545992.1A CN202010545992A CN111636082A CN 111636082 A CN111636082 A CN 111636082A CN 202010545992 A CN202010545992 A CN 202010545992A CN 111636082 A CN111636082 A CN 111636082A
Authority
CN
China
Prior art keywords
nuclear fuel
fuel cladding
alloy nuclear
coating
alloy
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202010545992.1A
Other languages
Chinese (zh)
Inventor
胡小刚
邱龙时
潘晓龙
张于胜
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Xian Rare Metal Materials Research Institute Co Ltd
Original Assignee
Xian Rare Metal Materials Research Institute Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Xian Rare Metal Materials Research Institute Co Ltd filed Critical Xian Rare Metal Materials Research Institute Co Ltd
Priority to CN202010545992.1A priority Critical patent/CN111636082A/en
Publication of CN111636082A publication Critical patent/CN111636082A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25D—PROCESSES FOR THE ELECTROLYTIC OR ELECTROPHORETIC PRODUCTION OF COATINGS; ELECTROFORMING; APPARATUS THEREFOR
    • C25D5/00—Electroplating characterised by the process; Pretreatment or after-treatment of workpieces
    • C25D5/34—Pretreatment of metallic surfaces to be electroplated
    • C25D5/38—Pretreatment of metallic surfaces to be electroplated of refractory metals or nickel
    • 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
    • C23C14/00—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
    • C23C14/06—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material characterised by the coating material
    • C23C14/14—Metallic material, boron or silicon
    • C23C14/16—Metallic material, boron or silicon on metallic substrates or on substrates of boron or silicon
    • 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
    • C23C14/00—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
    • C23C14/06—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material characterised by the coating material
    • C23C14/14—Metallic material, boron or silicon
    • C23C14/16—Metallic material, boron or silicon on metallic substrates or on substrates of boron or silicon
    • C23C14/165—Metallic material, boron or silicon on metallic substrates or on substrates of boron or silicon by cathodic sputtering
    • 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
    • C23C14/00—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
    • C23C14/22—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material characterised by the process of coating
    • C23C14/24—Vacuum evaporation
    • 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
    • C23C14/00—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
    • C23C14/22—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material characterised by the process of coating
    • C23C14/24—Vacuum evaporation
    • C23C14/32—Vacuum evaporation by explosion; by evaporation and subsequent ionisation of the vapours, e.g. ion-plating
    • C23C14/325—Electric arc evaporation
    • 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
    • C23C14/00—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
    • C23C14/22—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material characterised by the process of coating
    • C23C14/34—Sputtering
    • C23C14/3485—Sputtering using pulsed power to the target
    • 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
    • C23C14/00—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
    • C23C14/22—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material characterised by the process of coating
    • C23C14/34—Sputtering
    • C23C14/35—Sputtering by application of a magnetic field, e.g. magnetron sputtering
    • 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
    • C23C14/00—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material
    • C23C14/22—Coating by vacuum evaporation, by sputtering or by ion implantation of the coating forming material characterised by the process of coating
    • C23C14/48—Ion implantation
    • 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
    • C23C18/00—Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coating; Contact plating
    • C23C18/16—Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coating; Contact plating by reduction or substitution, e.g. electroless plating
    • 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
    • C23C24/00—Coating starting from inorganic powder
    • C23C24/02—Coating starting from inorganic powder by application of pressure only
    • C23C24/04—Impact or kinetic deposition of particles
    • 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
    • C23C28/00—Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of groups C23C2/00 - C23C26/00 or by combinations of methods provided for in subclasses C23C and C25C or C25D
    • C23C28/02—Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of groups C23C2/00 - C23C26/00 or by combinations of methods provided for in subclasses C23C and C25C or C25D only coatings only including layers of metallic material
    • 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
    • C23C28/00—Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of groups C23C2/00 - C23C26/00 or by combinations of methods provided for in subclasses C23C and C25C or C25D
    • C23C28/02—Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of groups C23C2/00 - C23C26/00 or by combinations of methods provided for in subclasses C23C and C25C or C25D only coatings only including layers of metallic material
    • C23C28/023—Coating for obtaining at least two superposed coatings either by methods not provided for in a single one of groups C23C2/00 - C23C26/00 or by combinations of methods provided for in subclasses C23C and C25C or C25D only coatings only including layers of metallic material only coatings of metal elements only
    • 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
    • C23C4/00—Coating by spraying the coating material in the molten state, e.g. by flame, plasma or electric discharge
    • C23C4/04—Coating by spraying the coating material in the molten state, e.g. by flame, plasma or electric discharge characterised by the coating material
    • C23C4/06—Metallic material
    • 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
    • C23F—NON-MECHANICAL REMOVAL OF METALLIC MATERIAL FROM SURFACE; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL; MULTI-STEP PROCESSES FOR SURFACE TREATMENT OF METALLIC MATERIAL INVOLVING AT LEAST ONE PROCESS PROVIDED FOR IN CLASS C23 AND AT LEAST ONE PROCESS COVERED BY SUBCLASS C21D OR C22F OR CLASS C25
    • C23F4/00—Processes for removing metallic material from surfaces, not provided for in group C23F1/00 or C23F3/00
    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25D—PROCESSES FOR THE ELECTROLYTIC OR ELECTROPHORETIC PRODUCTION OF COATINGS; ELECTROFORMING; APPARATUS THEREFOR
    • C25D3/00—Electroplating: Baths therefor
    • C25D3/02—Electroplating: Baths therefor from solutions
    • C25D3/04—Electroplating: Baths therefor from solutions of chromium
    • C25D3/06—Electroplating: Baths therefor from solutions of chromium from solutions of trivalent chromium
    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25D—PROCESSES FOR THE ELECTROLYTIC OR ELECTROPHORETIC PRODUCTION OF COATINGS; ELECTROFORMING; APPARATUS THEREFOR
    • C25D5/00—Electroplating characterised by the process; Pretreatment or after-treatment of workpieces
    • C25D5/10—Electroplating with more than one layer of the same or of different metals
    • C25D5/12—Electroplating with more than one layer of the same or of different metals at least one layer being of nickel or chromium
    • 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
    • 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

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Materials Engineering (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Mechanical Engineering (AREA)
  • Electrochemistry (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Chemical & Material Sciences (AREA)
  • Physical Vapour Deposition (AREA)

Abstract

The invention discloses a method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element, which comprises the following steps: firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding element; and secondly, carrying out electrochemical deposition Cr coating treatment on the surface-modified Zr alloy nuclear fuel cladding element to obtain the Zr alloy nuclear fuel cladding element with the Cr coating. According to the invention, the Zr alloy nuclear fuel cladding element is subjected to surface modification firstly, and then the accident tolerance Cr coating is deposited on the surface of the Zr alloy nuclear fuel cladding element subjected to surface modification through electrochemical deposition, so that the accident tolerance Cr coating is efficiently, low in cost and mass prepared on the outer surface of a pipe element, a plate element or a special-shaped element, the problem that the Cr coating cannot be directly electrochemically deposited due to no combination of the Zr alloy nuclear fuel cladding element and metal Cr in electroplating solution is solved, and the obtained Cr coating has the advantages of high thickness and accident resistance.

Description

Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element
Technical Field
The invention belongs to the technical field of nuclear power protection of thin film coatings, and particularly relates to a method for electrochemically preparing an accident fault-tolerant Cr coating of a nuclear fuel cladding element.
Background
In recent years, a large number of accident tolerance coatings of nuclear fuel cladding elements are prepared and researched at home and abroad, the base material of the nuclear fuel cladding elements is Zr alloy for nuclear use, the shape of the nuclear fuel cladding elements is in the form of pipe elements, plate elements or special-shaped elements, the demand of the nuclear fuel cladding elements is huge, the accident tolerance coatings gradually form a standard and are on-standby in large-scale application, the international advanced level represented by the United states adopts special physical vapor deposition to prepare pure Cr coatings, the thickness of the pure Cr coatings needs to be more than 15 mu m so as to meet the corrosion of the conventional service conditions and the high-temperature oxidation resistance requirements under accident conditions, and the physical vapor deposition is used as the most advanced technology in a surface coating means and has more defects, such as extremely low deposition rate, high deposition temperature, large stress and easy film collapse, expensive equipment cost, limited furnace loading amount by cavities, complicated coating process and the like, so that the production rate is low, The production and delivery of nuclear fuel cladding components are affected by the disadvantages of grain growth due to high temperature, increased cost, difficulty in equipment maintenance, difficulty in operator training, and the like.
The traditional trivalent Cr electroplating process can quickly prepare Cr coatings, has mature process and application market, has the thickness of hundreds of microns, has the advantages of high production efficiency, high deposition speed, low deposition temperature, simplicity in operation, low cost and the like, and can realize the plating production of special-shaped parts in various shapes. However, a large number of experimental results have shown that the Zr alloy has excellent corrosion resistance because the ZrO, which is dense and has low conductivity, is rapidly formed on the surface2And the potential difference between Cr and Zr does not accord with the electroplating principle, and the Cr coating cannot be effectively attached, so that the Cr coating cannot be directly electroplated on the surface of the Zr alloy. Therefore, a method for electrochemically preparing the accident-tolerant Cr coating on the Zr alloy nuclear fuel cladding component is needed.
Disclosure of Invention
The technical problem to be solved by the invention is to provide a method for electrochemically preparing accident-tolerant Cr coating of nuclear fuel cladding element, aiming at the defects of the prior art. The surface modification method firstly carries out surface modification on the Zr alloy nuclear fuel cladding element to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element, and then the accident tolerance Cr coating is deposited on the surface of the surface-modified Zr alloy nuclear fuel cladding element by adopting electrochemical deposition, so that the accident tolerance Cr coating is prepared on the surface of a pipe element, a plate element or a special-shaped element in a low-cost, high-efficiency and batch manner.
In order to solve the technical problems, the technical scheme provided by the invention is as follows: a method for electrochemically preparing accident-tolerant Cr coatings for nuclear fuel cladding components is characterized by comprising the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding element; the surface modification method comprises one or two of auxiliary anode etching, arc source high-pressure bombardment, physical vapor deposition, spraying, metal ion implantation, chemical deposition and electrochemical deposition;
and secondly, carrying out electrochemical deposition Cr coating treatment on the Zr alloy nuclear fuel cladding element subjected to surface modification in the step one to obtain the Zr alloy nuclear fuel cladding element with a Cr coating, wherein the thickness of the Cr coating is more than 10 microns.
According to the invention, the surface of the Zr alloy nuclear fuel cladding element is modified to form a modified layer, and then the electrochemical deposition of the Cr coating is carried out on the modified layer, so that the defect that the Cr coating cannot be deposited on the surface of the Zr alloy nuclear fuel cladding element by an electrochemical method in the prior art is solved, when the Zr alloy nuclear fuel cladding element is a tube element, the surface modification of the inner wall and the outer wall of the tube element is ensured to be carried out simultaneously, and the accident fault-tolerant Cr coating is prepared simultaneously, so that the accident fault-tolerant Cr coating is prepared on the surface of the nuclear fuel cladding element efficiently, at low cost and in batch, and the prepared Cr coating has the advantages of high thickness and loss nuclear accident resistance.
The method for electrochemically preparing the accident fault-tolerant Cr coating of the nuclear fuel cladding element is characterized in that in the step one, the auxiliary anode etching process comprises the following steps: and in an argon atmosphere, performing bombardment treatment on the surface of the Zr alloy nuclear fuel cladding element applied with a bias voltage of-600V to-1200V by using high-energy ion flow excited by the auxiliary anode, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element. The auxiliary anode etching is a means for improving the film-substrate bonding strength, ionization is carried out in an argon atmosphere, high-energy ion flow bombardment is carried out to remove an oxidation film on the surface of the Zr alloy nuclear fuel cladding element, and then a nano-micron order Cr film is deposited on the surface of the Zr alloy nuclear fuel cladding element, so that the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of a Cr coating is realized; according to the invention, by applying bias voltage, high-energy Ti ion flow or high-energy Cr ion flow is attracted to bombard the surface of the Zr alloy nuclear fuel cladding element, and the surface of the Zr alloy nuclear fuel cladding element is sputtered, so that the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of a Cr coating is realized.
The method for electrochemically preparing the accident fault-tolerant Cr coating of the nuclear fuel cladding element is characterized in that in the step one, the high-pressure bombardment process of the arc source comprises the following steps: and carrying out sputtering and deposition treatment on the surface of the Zr alloy nuclear fuel cladding element applied with the bias voltage of-500V to-1100V by using the plasma sprayed by the arc source, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element. The high-voltage bombardment of the arc source is an important means for improving the film-substrate bonding strength, bias voltage is applied to the Zr alloy nuclear fuel cladding element, the power density and energy of plasma are greatly improved, the surface of the Zr alloy nuclear fuel cladding element is accelerated to impact, an oxidation film or other pollutants on the surface of the Zr alloy nuclear fuel cladding element are removed, the purposes of cleaning and improving the bonding force are achieved, the energy density of the plasma jetted by the arc source is increased, the jetted plasma has double effects of sputtering and depositing on the surface of the Zr alloy nuclear fuel cladding element, the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of a Cr coating is realized.
The method for electrochemically preparing the accident fault-tolerant Cr coating of the nuclear fuel cladding element is characterized in that in the step one, the physical vapor deposition process comprises the following steps: carrying out deposition treatment on the surface of the Zr alloy nuclear fuel cladding element by adopting vacuum evaporation, multi-arc ion plating or magnetron sputtering; the vacuum evaporation process comprises the following steps: evaporating the metal wire into gas-phase atomic groups, and then carrying out deposition treatment on the surface of the Zr alloy nuclear fuel cladding element with the bias voltage of 0V-200V, so as to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element; the process of the multi-arc ion plating is as follows: exciting a metal target into plasma by adopting a cathode arc source, and then carrying out deposition treatment on the surface of the Zr alloy nuclear fuel cladding element with the bias voltage of-50V to-600V, so as to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element; the magnetron sputtering process comprises the following steps: after a high-power pulse magnetron sputtering power supply is adopted to excite a metal target into plasma, deposition treatment is carried out on the surface of the Zr alloy nuclear fuel cladding element with the bias voltage of-50V to-600V, and a modified layer is formed on the surface of the Zr alloy nuclear fuel cladding element. The metal wire is directly evaporated into gas phase by vacuum evaporation, and then is solidified and attached to the surface of the Zr alloy nuclear fuel cladding element to form a compact modified layer, bias voltage is applied to the Zr alloy nuclear fuel cladding element, and the metal capable of attracting the gas phase is deposited on the surface of the Zr alloy nuclear fuel cladding element to form a compact and strongly-combined metal layer, so that the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of a Cr coating is realized; the multi-arc ion plating excites a metal target into plasma through a cathode arc source under the condition of low voltage and high current, and then the plasma is dispersed in a chamber of a vacuum coating cavity, bias voltage is applied on the Zr alloy nuclear fuel cladding element, the plasma can be attracted to deposit on the surface of the Zr alloy nuclear fuel cladding element to form a dense and strongly-combined metal layer, so that the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of a Cr coating is realized; the metal target is excited into plasma by the magnetron sputtering power supply with high power pulse, bias voltage is applied to the Zr alloy nuclear fuel cladding element, the deposition effect is larger than the sputtering effect, and a metal layer is formed on the surface of the Zr alloy nuclear fuel cladding element, so that the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of the Cr coating is realized.
The method for electrochemically preparing the accident fault-tolerant Cr coating of the nuclear fuel cladding element is characterized in that the spraying process in the first step is as follows: and spraying metal powder on the surface of the Zr alloy nuclear fuel cladding element by adopting cold spraying or hot spraying, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element. The spraying can realize the spraying of the metal Cr layer on the surface of the Zr alloy nuclear fuel cladding element in a short time, is friendly to the shape of a matrix, and does not influence the grain change of the Zr alloy nuclear fuel cladding element, thereby achieving the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element and realizing the subsequent electrochemical deposition of the Cr coating.
The method for electrochemically preparing the accident fault-tolerant Cr coating of the nuclear fuel cladding element is characterized in that in the step one, the metal ion injection process comprises the following steps: injecting metal ions into the near-surface layer of the Zr alloy nuclear fuel cladding element to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element, wherein the injection depth of the metal ions is 50 nm-3 mu m. The metal ion injection method is different from other surface coating film adhesion methods, the performance modification is realized in the near-surface interior of the substrate by controlling the injection depth of the metal ions, no additional material is adhered, the elements are firmly combined to form metallurgical bonding, good film-substrate bonding force is provided for the preparation of the subsequent accident fault-tolerant fuel Cr coating, the thickness of the modification layer is controlled by controlling the injection depth, the purpose of modifying the surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of the Cr coating is realized.
The method for electrochemically preparing the accident-tolerant Cr coating of the nuclear fuel cladding element is characterized in that the chemical deposition process in the step one is as follows: and plating a metal film on the surface of the Zr alloy nuclear fuel cladding element by adopting chemical deposition, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element. The chemical deposition can quickly coat a metal film on the surface of the Zr alloy nuclear fuel cladding element, has the advantages of high deposition rate and reduction of the time required by production, realizes the simultaneous modification of the inner wall and the outer wall of the Zr alloy nuclear fuel cladding element with large length-diameter ratio, and completes the preparation of accident fault-tolerant fuel Cr coatings on the inner wall and the outer wall of the Zr alloy nuclear fuel cladding element, thereby achieving the purpose of modifying the inner surface and the outer surface of the Zr alloy nuclear fuel cladding element and realizing the subsequent electrochemical deposition of the Cr coatings.
The method for electrochemically preparing the accident-tolerant Cr coating of the nuclear fuel cladding element is characterized in that in the step one, the electrochemical deposition process comprises the following steps: and plating a metal film on the surface of the Zr alloy nuclear fuel cladding element by adopting electrochemical deposition, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element. The electrochemical deposition can quickly coat a metal film on the surface of the Zr alloy nuclear fuel cladding element, and has the advantages of high deposition rate and reduction of the time required by production, the electrochemical deposition realizes the simultaneous modification of the inner wall and the outer wall of the Zr alloy nuclear fuel cladding element with large length-diameter ratio, and the preparation of accident fault-tolerant fuel Cr coatings on the inner wall and the outer wall of the Zr alloy nuclear fuel cladding element is completed, so that the purpose of modifying the inner surface and the outer surface of the Zr alloy nuclear fuel cladding element is achieved, and the subsequent electrochemical deposition of the Cr coatings is realized.
The method for electrochemically preparing the accident fault-tolerant Cr coating of the nuclear fuel cladding element is characterized in that in the second step, a trivalent Cr electroplating process is adopted for electrochemically depositing the Cr coating. The invention realizes electrochemical deposition of Cr by adopting a trivalent Cr electroplating process, realizes uniform electrochemical deposition of a Cr coating on the surface of the Zr alloy nuclear fuel cladding element, and has the advantages of low cost, easy operation, no toxicity, no pollution and little environmental hazard.
The principle of the invention for electrochemically preparing the accident fault-tolerant Cr coating of the nuclear fuel cladding element is as follows: the Zr alloy surface is easy to generate compact ZrO with low conductivity2The invention firstly carries out surface modification on the Zr alloy, changes the surface state of the Zr alloy, and in the subsequent electroplating process, the redox reaction in the electroplating solution does not face Zr element any more, but the modified metal materials are as follows: cr, Ti, Ni or Pd, which conform to the principle of electroplating potential difference, and then plating an accident fault-tolerant fuel coating Cr with accident resistance on the surface of the Zr alloy by adopting a mature electrochemical method; the Cr coating can generate a layer of compact Cr at high temperature2O3The Cr coating layer of the present invention has a thickness of more than 10 μm and can resist the peeling of the oxide film at least 1.5 times.
Compared with the prior art, the invention has the following advantages:
1. the surface modification method adopts one or two of auxiliary anode etching, arc source high-pressure bombardment, physical vapor deposition, spraying, metal ion injection, chemical deposition and electrochemical deposition to carry out surface modification on the Zr alloy nuclear fuel cladding element, can form a modified layer on the surface of the Zr alloy nuclear fuel cladding element, is suitable for surface modification of a pipe element, a plate element or a special-shaped element, ensures that the inner wall and the outer wall of the pipe element are simultaneously subjected to surface modification, enhances the applicability of the surface modification method, avoids the defect of high production cost caused by directly using the method to prepare the Cr coating, and simultaneously avoids the defect that the Cr coating cannot be prepared on the inner wall of the pipe element.
2. According to the invention, the surface of the Zr alloy nuclear fuel cladding element is modified to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element, and then the electrochemical deposition Cr coating treatment is carried out on the modified layer to obtain the Zr alloy nuclear fuel cladding element with the Cr coating, so that the defect that the Cr coating cannot be deposited on the surface of the Zr alloy nuclear fuel cladding element by an electrochemical method in the prior art is overcome, the accident fault-tolerant Cr coating is prepared on the surfaces of the nuclear fuel cladding elements in various shapes efficiently, at low cost and in batch, and the prepared Cr coating has the advantages of high thickness and nuclear loss accident resistance.
3. The invention realizes electrochemical deposition of Cr by adopting a trivalent Cr electroplating process, realizes uniform electrochemical deposition of a Cr coating on the surface of the Zr alloy nuclear fuel cladding element, reduces the production cost, and has the advantages of no toxicity, no pollution, small environmental hazard, wide application range and easy popularization.
4. The method is simple to operate and easy to realize, can effectively meet the requirement of electrochemical deposition of the Cr coating on the surface of the Zr alloy nuclear fuel cladding element in practical production, and can realize large-scale production.
The technical solution of the present invention is further described in detail by the accompanying drawings and examples.
Drawings
FIG. 1 is a schematic structural view of a Zr alloy nuclear fuel cladding plate member with a Cr coating according to example 1 of the present invention.
Fig. 2 is a schematic structural view of a Zr alloy nuclear fuel cladding tube element with a Cr coating according to example 2 of the present invention.
Description of reference numerals:
1-Zr alloy nuclear fuel cladding plate elements; 2-Cr modified layer; 3-Cr coating;
a 4-Zr alloy nuclear fuel cladding tube element; 5-Pd modified layer.
Detailed Description
The present invention is described in detail in examples 1 to 29.
Example 1
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting auxiliary anode etching; the auxiliary anode etching process comprises the following steps: exciting metal Cr into Cr particle flow under the condition of 1Pa under the power supply of 20V 100A in the argon atmosphere, then bombarding and sputtering the surface of a Zr alloy nuclear fuel cladding plate with-750V bias voltage for 120min by the Cr particle flow, and obtaining a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the metal Cr and the Zr alloy nuclear fuel cladding plate element is 200 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was determined to be 100nm and the thickness of the Cr coating was determined to be 15 μm.
Fig. 1 is a schematic structural view of a Zr alloy nuclear fuel cladding plate member with Cr coating according to the present embodiment, and it can be seen from fig. 1 that the surface of Zr alloy nuclear fuel cladding plate member 1 is uniformly coated with a Cr modified layer 2, and the Cr modified layer 2 is uniformly coated with a Cr coating 3.
Example 2
Firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding tube element by adopting chemical deposition; the chemical deposition process comprises the following steps: placing a Zr alloy nuclear fuel cladding tube element into a Pd-containing vessel2+The activation solution is treated, and Pd modified layers are obtained on the inner wall and the outer wall of the Zr alloy nuclear fuel cladding tube element;
step two, cleaning the Zr alloy nuclear fuel cladding tube element subjected to surface modification in the step one in deionized water, and then putting the cleaned Zr alloy nuclear fuel cladding tube element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding tube element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Pd modified layer in this example was measured to be 50nm, and the thickness of the Cr coating was measured to be 11 μm.
Fig. 2 is a schematic structural view of the Zr alloy nuclear fuel cladding element with Cr coating according to this example, and it can be seen from fig. 2 that both the outer and inner walls of the Zr alloy nuclear fuel cladding element 4 are coated with a Pd modified layer 5, and the Pd modified layer 5 is coated with a Cr coating 3.
Example 3
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting auxiliary anode etching; the auxiliary anode etching process comprises the following steps: exciting metal Cr to form Cr particle flow under the power supply of 20V 100A under the condition of 2Pa under the argon atmosphere, then bombarding and sputtering the surface of a Zr alloy nuclear fuel cladding plate applied with-1200V bias voltage for 120min by the Cr particle flow, and obtaining a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the metal Cr and the Zr alloy nuclear fuel cladding plate element is 200 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was 2 μm and the thickness of the Cr coating was 15 μm.
Example 4
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting auxiliary anode etching; the auxiliary anode etching process comprises the following steps: exciting Ti particle flow by using metal Ti under the condition of the pressure of 3Pa under the argon atmosphere under the power supply of 10V 100A, then bombarding and sputtering the Ti particle flow on the surface of a Zr alloy nuclear fuel cladding plate applied with-600V bias voltage for 120min, and obtaining a Ti modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the metal Ti and the Zr alloy nuclear fuel cladding plate element is 200 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was found to be 50nm, and the thickness of the Cr coating was found to be 15 μm.
Example 5
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate element by adopting high-pressure bombardment of an arc source; the high-pressure bombardment process of the arc source comprises the following steps: under the condition of argon atmosphere and pressure of 0.5Pa, a cathode arc source is adopted to spray Cr plasma to sputter and deposit the surface of the Zr alloy nuclear fuel cladding plate element with-700V bias voltage, and a Cr modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate element;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was measured to be 500nm, and the thickness of the Cr coating was measured to be 16 μm.
Example 6
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate element by adopting high-pressure bombardment of an arc source; the high-pressure bombardment process of the arc source comprises the following steps: under the condition of argon atmosphere and pressure of 0.5Pa, a cathode arc source is adopted to spray Cr plasma to sputter and deposit the surface of the Zr alloy nuclear fuel cladding plate element with-1000V bias voltage, and a Cr modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate element;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was 2 μm and the thickness of the Cr coating was 16 μm.
Example 7
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate element by adopting high-pressure bombardment of an arc source; the high-pressure bombardment process of the arc source comprises the following steps: under the condition of argon atmosphere and pressure of 0.5Pa, a cathode arc source is adopted to spray Ti plasma to sputter and deposit the surface of the Zr alloy nuclear fuel cladding plate element with-500V bias voltage, and a Ti modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate element;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was found to be 50nm, and the thickness of the Cr coating was found to be 16 μm.
Example 8
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting vacuum evaporation; the vacuum evaporation process comprises the following steps: under the condition of argon atmosphere and pressure intensity of 0.1Pa, adopting 10KV high voltage to match with high-frequency discharge, evaporating 5N-grade high-purity Cr metal wires into gas-phase Cr atomic groups, then depositing the gas-phase Cr atomic groups on the surface of a Zr alloy nuclear fuel cladding plate element, and obtaining a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the 5N-grade high-purity Cr metal wires and the Zr alloy nuclear fuel cladding plate element is 50 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 1 μm, and the thickness of the Cr coating was found to be 15 μm.
Example 9
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting vacuum evaporation; the vacuum evaporation process comprises the following steps: under the condition of argon atmosphere and pressure of 0.1Pa, adopting 10KV high voltage to match with high-frequency discharge, evaporating 5N-grade high-purity Ti metal wires into gas-phase Ti atomic groups, then depositing the gas-phase Ti atomic groups on the surface of a Zr alloy nuclear fuel cladding plate element applied with-200V bias voltage, and obtaining a Ti modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the 5N-grade high-purity Ti metal wires and the Zr alloy nuclear fuel cladding plate element is 50 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was 2 μm and the thickness of the Cr coating was 15 μm.
Example 10
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting vacuum evaporation; the vacuum evaporation process comprises the following steps: under the condition of argon atmosphere and pressure of 0.1Pa, adopting 10KV high voltage to match with high-frequency discharge, evaporating 5N-grade high-purity Cr metal wires into gas-phase Cr atomic groups, then depositing the gas-phase Cr atomic groups on the surface of a Zr alloy nuclear fuel cladding plate element applied with-100V bias voltage, and obtaining a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the 5N-grade high-purity Cr metal wires and the Zr alloy nuclear fuel cladding plate element is 50 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 50nm, and the thickness of the Cr coating was found to be 15 μm.
Example 11
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate component by adopting multi-arc ion plating; the process of the multi-arc ion plating is as follows: exciting a Cr target into Cr plasma by adopting a cathode arc source under the condition of 0.5Pa under the argon atmosphere, depositing the Cr plasma on a Zr alloy nuclear fuel cladding plate element applied with-120V bias voltage, and obtaining a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the Cr target and the Zr alloy nuclear fuel cladding plate element is 180 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 300nm, and the thickness of the Cr coating was found to be 16 μm.
Example 12
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate component by adopting multi-arc ion plating; the process of the multi-arc ion plating is as follows: exciting a Ti target into Ti plasma by adopting a cathode arc source under the condition of 0.5Pa in the argon atmosphere, depositing the Ti plasma on a Zr alloy nuclear fuel cladding plate element applied with-50V bias voltage, and obtaining a Ti modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the Ti target and the Zr alloy nuclear fuel cladding plate element is 180 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was found to be 50nm, and the thickness of the Cr coating was found to be 16 μm.
Example 13
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate component by adopting multi-arc ion plating; the process of the multi-arc ion plating is as follows: exciting a Ti target into Ti plasma by adopting a cathode arc source under the condition of 0.5Pa in the argon atmosphere, depositing the Ti plasma on a Zr alloy nuclear fuel cladding plate element applied with-600V bias voltage, and obtaining a Ti modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the Ti target and the Zr alloy nuclear fuel cladding plate element is 180 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was found to be 5 μm, and the thickness of the Cr coating was found to be 16 μm.
Example 14
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting magnetron sputtering; the magnetron sputtering process comprises the following steps: under the condition of argon atmosphere and pressure intensity of 0.8Pa, a high-power pulse magnetron sputtering power supply is adopted to excite a 5N-grade Cr columnar target into Cr plasma with the power of 30kW, then the Cr plasma is deposited on a Zr alloy nuclear fuel cladding plate component applied with-100V bias voltage, and a Cr modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate component, wherein the distance between the Cr columnar target and the Zr alloy nuclear fuel cladding plate component is 50 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 300nm, and the thickness of the Cr coating was found to be 16 μm.
Example 15
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting magnetron sputtering; the magnetron sputtering process comprises the following steps: under the condition of argon atmosphere and pressure intensity of 0.8Pa, a high-power pulse magnetron sputtering power supply is adopted to excite a 5N-grade Ti columnar target into Ti plasma with the power of 30kW, then the Ti plasma is deposited on a Zr alloy nuclear fuel cladding plate element applied with-50V bias voltage, and a Ti modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the distance between the Ti columnar target and the Zr alloy nuclear fuel cladding plate element is 50 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was found to be 50nm, and the thickness of the Cr coating was found to be 16 μm.
Example 16
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting magnetron sputtering; the magnetron sputtering process comprises the following steps: under the condition of argon atmosphere and pressure intensity of 0.8Pa, a high-power pulse magnetron sputtering power supply is adopted to excite a 5N-grade Cr columnar target into Cr plasma with the power of 30kW, then the Cr plasma is deposited on a Zr alloy nuclear fuel cladding plate component applied with-600V bias voltage, and a Cr modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate component, wherein the distance between the Cr columnar target and the Zr alloy nuclear fuel cladding plate component is 50 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 5 μm, and the thickness of the Cr coating was found to be 16 μm.
Example 17
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate element by adopting cold spraying; the cold spraying process comprises the following steps: under the condition of argon atmosphere and 20 ℃ of temperature, 5N-grade Cr powder with the particle size of 50nm is sprayed on the surface of the Zr alloy nuclear fuel cladding plate component by supersonic gas and solid two-phase gas flow, and a Cr modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate component;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 5 μm, and the thickness of the Cr coating was found to be 17 μm.
Example 18
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate component by adopting supersonic flame spraying; the supersonic flame spraying process comprises the following steps: under argon atmosphere, spraying 5N-grade Ti powder with the particle size of 50nm onto the surface of a Zr alloy nuclear fuel cladding plate element after being heated and accelerated by supersonic high-temperature flame flow, and obtaining a Ti modified layer on the surface of the Zr alloy nuclear fuel cladding plate element;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was found to be 4 μm and the thickness of the Cr coating was found to be 17 μm.
Example 19
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting plasma spraying; the plasma spraying process comprises the following steps: under argon atmosphere, 5N-grade Cr powder with the grain size of 50nm is subjected to plasma-assisted heating and melting and then sprayed on the surface of the Zr alloy nuclear fuel cladding plate component, and a Cr modified layer is obtained on the surface of the Zr alloy nuclear fuel cladding plate component;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was 2 μm and the thickness of the Cr coating was 17 μm.
Example 20
The embodiment comprises the following steps:
step one, adopting metal ions to the Zr alloy nuclear fuel cladding plate elementInjecting Cr element to the near surface of the Zr alloy nuclear fuel cladding plate element by using a metal vapor vacuum arc ion source under the condition of the pressure of 3Pa and the argon atmosphere to obtain a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the injection energy is 80keV, and the injection dosage is 3 × 1017/cm2The implantation depth is 50 nm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was determined to be 100nm and the thickness of the Cr coating was determined to be 15 μm.
Example 21
The embodiment comprises the following steps:
the method comprises the following steps of firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting metal ion implantation, wherein the metal ion implantation process comprises the steps of implanting Ti element into the near surface of the Zr alloy nuclear fuel cladding plate element by adopting a metal steam vacuum arc ion source under the condition of 3Pa and the argon atmosphere, and obtaining a Ti modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the implantation energy is 80keV, and the implantation dosage is 5 × 1017/cm2The implantation depth is 1 μm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ti modified layer in this example was 2 μm and the thickness of the Cr coating was 15 μm.
Example 22
The embodiment comprises the following steps:
step one, mixing ZrThe surface modification of the gold nuclear fuel cladding plate element is carried out by adopting metal ion implantation, wherein the metal ion implantation process comprises the steps of implanting Cr element into the near surface of the Zr alloy nuclear fuel cladding plate element by adopting a metal steam vacuum arc ion source under the conditions of argon atmosphere and 3Pa, and obtaining a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the implantation energy is 80keV, and the implantation dosage is 8 × 1017/cm2The injection depth is 3 μm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 5 μm, and the thickness of the Cr coating was found to be 15 μm.
Example 23
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate element by adopting electrochemical deposition; the electrochemical deposition process comprises the following steps: adopting a direct current superimposed pulse power supply, taking a 5N-grade Ni block as an anode and a Zr alloy nuclear fuel cladding plate element as a cathode, electrochemically plating Ni on the surface of the Zr alloy nuclear fuel cladding plate element by using a watt nickel plating solution, and obtaining a Ni modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the current density is 35A/dm2The distance between the anode and the cathode is 100mm, the temperature is 85 ℃, and the deposition time is 15 min;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ni modified layer in this example was 2 μm and the thickness of the Cr coating was 11 μm.
Example 24
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate element by adopting electrochemical deposition; the electrochemical deposition process comprises the following steps: adopting a direct current superimposed pulse power supply, taking a 5N-grade Ni block as an anode and a Zr alloy nuclear fuel cladding plate element as a cathode, electrochemically plating Ni on the surface of the Zr alloy nuclear fuel cladding plate element by using a watt nickel plating solution, and obtaining a Ni modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the current density is 35A/dm2The distance between the anode and the cathode is 100mm, the temperature is 85 ℃, and the deposition time is 5 min;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ni modified layer in this example was found to be 50nm and the thickness of the Cr coating was found to be 11 μm.
Example 25
The embodiment comprises the following steps:
firstly, performing surface modification on a Zr alloy nuclear fuel cladding plate element by adopting electrochemical deposition; the electrochemical deposition process comprises the following steps: adopting a direct current superimposed pulse power supply, taking a 5N-grade Ni block as an anode and a Zr alloy nuclear fuel cladding plate element as a cathode, electrochemically plating Ni on the surface of the Zr alloy nuclear fuel cladding plate element by using a watt nickel plating solution, and obtaining a Ni modified layer on the surface of the Zr alloy nuclear fuel cladding plate element, wherein the current density is 35A/dm2The distance between the anode and the cathode is 100mm, the temperature is 85 ℃, and the deposition time is 30 min;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ni modified layer in this example was found to be 5 μm and the thickness of the Cr coating was found to be 11 μm.
Example 26
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding L-shaped plate element by adopting electrochemical deposition; the electrochemical deposition process comprises the following steps: adopting a direct current superimposed pulse power supply, taking a 5N-grade Ni block as an anode, taking a Zr alloy nuclear fuel cladding L-shaped plate element as a cathode, using a watt nickel plating solution to electrochemically plate Ni on the surface of the Zr alloy nuclear fuel cladding L-shaped plate element, and obtaining a Ni modified layer on the surface of the Zr alloy nuclear fuel cladding L-shaped plate element, wherein the current density is 35A/dm2The distance between the anode and the cathode is 100mm, the temperature is 85 ℃, and the deposition time is 30 min;
step two, cleaning the Zr alloy nuclear fuel cladding L-shaped plate element subjected to surface modification in the step one in deionized water, and then placing the cleaned Zr alloy nuclear fuel cladding L-shaped plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding L-shaped plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Ni modified layer in this example was found to be 5 μm and the thickness of the Cr coating was found to be 11 μm.
Example 27
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding tube element by adopting chemical deposition; the chemical deposition process comprises the following steps: placing a Zr alloy nuclear fuel cladding tube element into a Pd-containing vessel2+The activation solution is treated, and Pd modified layers are obtained on the inner wall and the outer wall of the Zr alloy nuclear fuel cladding tube element;
step two, cleaning the Zr alloy nuclear fuel cladding tube element subjected to surface modification in the step one in deionized water, and then putting the cleaned Zr alloy nuclear fuel cladding tube element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding tube element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Pd modified layer in this example was 2 μm and the thickness of the Cr coating was 11 μm.
Example 28
Firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding tube element by adopting chemical deposition; the chemical deposition process comprises the following steps: placing a Zr alloy nuclear fuel cladding tube element into a Pd-containing vessel2+The activation solution is treated, and Pd modified layers are obtained on the inner wall and the outer wall of the Zr alloy nuclear fuel cladding tube element;
step two, cleaning the Zr alloy nuclear fuel cladding tube element subjected to surface modification in the step one in deionized water, and then putting the cleaned Zr alloy nuclear fuel cladding tube element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding tube element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Pd modified layer in this example was measured to be 5 μm, and the thickness of the Cr coating was measured to be 11 μm.
Example 29
The embodiment comprises the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding plate element by adopting auxiliary anode etching and multi-arc ion plating; the auxiliary anode etching and physical vapor deposition process comprises the following steps: exciting metal Cr into Cr particle flow under the condition of 2Pa pressure in the argon atmosphere, bombarding and sputtering the surface of a Zr alloy nuclear fuel cladding plate applied with-600V bias voltage for 60min by the Cr particle flow, exciting the metal Cr into Cr plasma by adopting a cathode arc source, depositing the Zr alloy nuclear fuel cladding plate applied with-400V bias voltage by the Cr plasma, and obtaining a Cr modified layer on the surface of the Zr alloy nuclear fuel cladding plate, wherein the distance between the metal Cr and the Zr alloy nuclear fuel cladding plate is 200 mm;
step two, cleaning the Zr alloy nuclear fuel cladding plate element subjected to surface modification in the step one in deionized water, and then putting the Zr alloy nuclear fuel cladding plate element into a chromium plating solution for carrying out electrochemical deposition Cr coating treatment to obtain the Zr alloy nuclear fuel cladding plate element with a Cr coating; the chromium plating solution comprises 250g/L of chromic anhydride and 1.8g/L of sulfuric acid.
The thickness of the Cr modified layer in this example was found to be 1 μm, and the thickness of the Cr coating was found to be 15 μm.
The above description is only for the preferred embodiment of the present invention, and is not intended to limit the present invention in any way. Any simple modification, change and equivalent changes of the above embodiments according to the technical essence of the invention are still within the protection scope of the technical solution of the invention.

Claims (9)

1. A method for electrochemically preparing accident-tolerant Cr coatings for nuclear fuel cladding components is characterized by comprising the following steps:
firstly, carrying out surface modification on a Zr alloy nuclear fuel cladding element; the surface modification method comprises one or two of auxiliary anode etching, arc source high-pressure bombardment, physical vapor deposition, spraying, metal ion implantation, chemical deposition and electrochemical deposition;
and secondly, carrying out electrochemical deposition Cr coating treatment on the Zr alloy nuclear fuel cladding element subjected to surface modification in the step one to obtain the Zr alloy nuclear fuel cladding element with a Cr coating, wherein the thickness of the Cr coating is more than 10 microns.
2. The method for electrochemically preparing accident tolerant Cr coating for nuclear fuel cladding elements according to claim 1, wherein the auxiliary anodic etching in step one comprises: and in an argon atmosphere, performing bombardment treatment on the surface of the Zr alloy nuclear fuel cladding element applied with a bias voltage of-600V to-1200V by using high-energy ion flow excited by the auxiliary anode, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element.
3. The method for electrochemically preparing accident-tolerant Cr coating for nuclear fuel cladding elements according to claim 1, wherein the high-voltage bombardment process of the arc source in the first step is as follows: and carrying out sputtering and deposition treatment on the surface of the Zr alloy nuclear fuel cladding element applied with the bias voltage of-500V to-1100V by using the plasma sprayed by the arc source, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element.
4. The method for electrochemically preparing accident-tolerant Cr coating for nuclear fuel cladding elements according to claim 1, wherein the physical vapor deposition process in step one is as follows: carrying out deposition treatment on the surface of the Zr alloy nuclear fuel cladding element by adopting vacuum evaporation, multi-arc ion plating or magnetron sputtering; the vacuum evaporation process comprises the following steps: evaporating the metal wire into gas-phase atomic groups, and then carrying out deposition treatment on the surface of the Zr alloy nuclear fuel cladding element with the bias voltage of 0V-200V, so as to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element; the process of the multi-arc ion plating is as follows: exciting a metal target into plasma by adopting a cathode arc source, and then carrying out deposition treatment on the surface of the Zr alloy nuclear fuel cladding element with the bias voltage of-50V to-600V, so as to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element; the magnetron sputtering process comprises the following steps: after a high-power pulse magnetron sputtering power supply is adopted to excite a metal target into plasma, deposition treatment is carried out on the surface of the Zr alloy nuclear fuel cladding element with the bias voltage of-50V to-600V, and a modified layer is formed on the surface of the Zr alloy nuclear fuel cladding element.
5. The method for electrochemically preparing accident-tolerant Cr coating for nuclear fuel cladding components according to claim 1, wherein the spraying in step one comprises: and spraying metal powder on the surface of the Zr alloy nuclear fuel cladding element by adopting cold spraying or hot spraying, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element.
6. The method for electrochemically preparing accident-tolerant Cr coating for nuclear fuel cladding elements according to claim 1, wherein the metal ion implantation in step one comprises: injecting metal ions into the near-surface layer of the Zr alloy nuclear fuel cladding element to form a modified layer on the surface of the Zr alloy nuclear fuel cladding element, wherein the injection depth of the metal ions is 50 nm-3 mu m.
7. The method for electrochemically preparing accident-tolerant Cr coating for nuclear fuel cladding elements according to claim 1, wherein the chemical deposition process in step one is as follows: and plating a metal film on the surface of the Zr alloy nuclear fuel cladding element by adopting chemical deposition, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element.
8. The method for electrochemically preparing accident-tolerant Cr coating for nuclear fuel cladding elements according to claim 1, wherein the electrochemical deposition process in step one is as follows: and plating a metal film on the surface of the Zr alloy nuclear fuel cladding element by adopting electrochemical deposition, and forming a modified layer on the surface of the Zr alloy nuclear fuel cladding element.
9. The method of electrochemically preparing accident tolerant Cr coating for nuclear fuel cladding components according to claim 1, wherein in step two the electrochemically deposited Cr coating is applied by a trivalent Cr electroplating process.
CN202010545992.1A 2020-06-16 2020-06-16 Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element Pending CN111636082A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202010545992.1A CN111636082A (en) 2020-06-16 2020-06-16 Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202010545992.1A CN111636082A (en) 2020-06-16 2020-06-16 Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element

Publications (1)

Publication Number Publication Date
CN111636082A true CN111636082A (en) 2020-09-08

Family

ID=72326918

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202010545992.1A Pending CN111636082A (en) 2020-06-16 2020-06-16 Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element

Country Status (1)

Country Link
CN (1) CN111636082A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112899682A (en) * 2021-01-20 2021-06-04 哈尔滨工业大学 Preparation method of zirconium cladding protective coating
CN113388811A (en) * 2021-05-10 2021-09-14 中国科学院金属研究所 Double-layer Cr/Cr for accident fault-tolerant fuel cladding2AlC coating and preparation method thereof
CN114232052A (en) * 2020-09-09 2022-03-25 北京师范大学 Preparation method of high-temperature corrosion resistant composite coating on surface of zirconium alloy cladding
CN117305805A (en) * 2023-09-27 2023-12-29 上海交通大学 Nuclear fuel cladding modification method based on nano diamond coating

Citations (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010128691A1 (en) * 2009-05-04 2010-11-11 포항공과대학교 산학협력단 Method for forming fine protrusions on cladding surface of nuclear fuel rod containing zirconium
US20130220493A1 (en) * 2012-02-28 2013-08-29 Korea Hydro And Nuclear Power Co., Ltd. Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a reactor accident condition, zirconium alloy nuclear fuel claddings prepared by using thereof and methods of preparing the same
US20150050521A1 (en) * 2012-04-26 2015-02-19 Commissariat A L'energie Atomique Et Aux Energies Alternatives Multilayer material resistant to oxidation in a nuclear environment
US20150131768A1 (en) * 2013-11-13 2015-05-14 Areva Np Inc. Nuclear fuel rod cladding including a metal nanomaterial layer
US20150348652A1 (en) * 2014-05-27 2015-12-03 Westinghouse Electric Company Llc Deposition of a protective coating including metal-containing and chromium-containing layers on zirconium alloy for nuclear power applications
US20170287578A1 (en) * 2014-09-17 2017-10-05 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear fuel claddings, production method thereof and uses of same against oxidation/hydriding
US20180096743A1 (en) * 2016-10-03 2018-04-05 Westinghouse Electric Company, Llc Duplex accident tolerant coating for nuclear fuel rods
EP3502321A1 (en) * 2017-12-20 2019-06-26 Westinghouse Electric Sweden AB Method of forming a coated component made of zirconium or zirconium-based alloy
CN109972098A (en) * 2019-05-05 2019-07-05 大连理工大学 A kind of preparation method of cladding materials surface C rN thick coating
CN110106467A (en) * 2019-06-25 2019-08-09 中国核动力研究设计院 A kind of used by nuclear reactor efficiently combines clad and preparation method thereof
CN110184605A (en) * 2019-06-25 2019-08-30 中国核动力研究设计院 A kind of used by nuclear reactor outer surface clad and preparation method thereof
CN110777336A (en) * 2019-09-20 2020-02-11 西安稀有金属材料研究院有限公司 Method for preparing ultra-thick hard film based on energy regulation and control principle

Patent Citations (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010128691A1 (en) * 2009-05-04 2010-11-11 포항공과대학교 산학협력단 Method for forming fine protrusions on cladding surface of nuclear fuel rod containing zirconium
US20130220493A1 (en) * 2012-02-28 2013-08-29 Korea Hydro And Nuclear Power Co., Ltd. Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a reactor accident condition, zirconium alloy nuclear fuel claddings prepared by using thereof and methods of preparing the same
US20150050521A1 (en) * 2012-04-26 2015-02-19 Commissariat A L'energie Atomique Et Aux Energies Alternatives Multilayer material resistant to oxidation in a nuclear environment
US20150131768A1 (en) * 2013-11-13 2015-05-14 Areva Np Inc. Nuclear fuel rod cladding including a metal nanomaterial layer
US20150348652A1 (en) * 2014-05-27 2015-12-03 Westinghouse Electric Company Llc Deposition of a protective coating including metal-containing and chromium-containing layers on zirconium alloy for nuclear power applications
CN106460194A (en) * 2014-05-27 2017-02-22 西屋电气有限责任公司 Deposition of a protective coating including metal-containing and chromium-containing layers on zirconium alloy for nuclear power applications
US20170287578A1 (en) * 2014-09-17 2017-10-05 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear fuel claddings, production method thereof and uses of same against oxidation/hydriding
US20180096743A1 (en) * 2016-10-03 2018-04-05 Westinghouse Electric Company, Llc Duplex accident tolerant coating for nuclear fuel rods
EP3502321A1 (en) * 2017-12-20 2019-06-26 Westinghouse Electric Sweden AB Method of forming a coated component made of zirconium or zirconium-based alloy
CN109972098A (en) * 2019-05-05 2019-07-05 大连理工大学 A kind of preparation method of cladding materials surface C rN thick coating
CN110106467A (en) * 2019-06-25 2019-08-09 中国核动力研究设计院 A kind of used by nuclear reactor efficiently combines clad and preparation method thereof
CN110184605A (en) * 2019-06-25 2019-08-30 中国核动力研究设计院 A kind of used by nuclear reactor outer surface clad and preparation method thereof
CN110777336A (en) * 2019-09-20 2020-02-11 西安稀有金属材料研究院有限公司 Method for preparing ultra-thick hard film based on energy regulation and control principle

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114232052A (en) * 2020-09-09 2022-03-25 北京师范大学 Preparation method of high-temperature corrosion resistant composite coating on surface of zirconium alloy cladding
CN114232052B (en) * 2020-09-09 2023-03-10 北京师范大学 Preparation method of high-temperature corrosion resistant composite coating on surface of zirconium alloy cladding
CN112899682A (en) * 2021-01-20 2021-06-04 哈尔滨工业大学 Preparation method of zirconium cladding protective coating
CN113388811A (en) * 2021-05-10 2021-09-14 中国科学院金属研究所 Double-layer Cr/Cr for accident fault-tolerant fuel cladding2AlC coating and preparation method thereof
CN117305805A (en) * 2023-09-27 2023-12-29 上海交通大学 Nuclear fuel cladding modification method based on nano diamond coating

Similar Documents

Publication Publication Date Title
CN111636082A (en) Method for electrochemically preparing accident fault-tolerant Cr coating of nuclear fuel cladding element
CN109778136B (en) Method for preparing diamond-like coating by adopting thermionic plasma technology
CN103498128B (en) Magnetic control sputtering film plating device and film plating process
CN107164731B (en) Preparation method of aluminum composite protective layer on surface of magnesium alloy
CN103668095A (en) High-power pulse plasma reinforced composite magnetron sputtering deposition device and application method thereof
CN102409293A (en) Preparation method of alumina film
CN103360122A (en) Method for improving metalized surface performance of ceramic workpiece
CN102492924A (en) Autologous ion bombardment assisted electron beam evaporation device, and method for coating film by using same
CN103469164B (en) Device and method for realizing plasma activation electron beam physical vapor deposition
TWI677589B (en) A preparation method of sputtering target
CN100395371C (en) Apparatus for reinforcing arc-glow percolation plated ceating by microwave plasma and process thereof
CN101403101A (en) Quick solid-ceramic coating ion plating apparatus
CN100582290C (en) Method for plating stainless steel protective cover on NdFeB magnet surface with magnetic controlled electrical arc ion
CN109680250B (en) Arc ion source and arc ion source coating method
RU2407820C1 (en) Procedure for application of coating on items out of ceramics in vacuum
CN116288201A (en) Iron-carbon alloy target and film preparation method thereof
CN116219374A (en) Device and method for improving surface finish and film-based bonding strength of inner wall coating of pipe barrel
CN115786847A (en) Method for performing magnetron sputtering in elongated tube by using direct-current composite bipolar pulse
CN109972108A (en) A kind of Nanostructured Ceramic Coatings and its in-situ preparation method and application
CN105112872A (en) Pulse magnetron sputtering device for preparing inner surface coating of cylinder part and application of pulse magnetron sputtering device
RU2566232C1 (en) Method of combined ion-plasma treatment of products out of aluminium alloys
CN108165944A (en) A kind of super thick Ti2The preparation method of AlC coatings
CN114086143A (en) Substrate coating process
CN108149197B (en) Method for manufacturing reflecting plate of laser generator
US20050016833A1 (en) Plasma sprayed indium tin oxide target for sputtering

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
RJ01 Rejection of invention patent application after publication
RJ01 Rejection of invention patent application after publication

Application publication date: 20200908