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Coating layer for high-efficient combination of nuclear reactor and preparation method of coating layer

A nuclear reactor and cladding technology, applied in coating, sputtering, ion implantation, etc., can solve problems such as potential safety hazards, achieve good corrosion resistance, good control of composition and phase structure, and good film-base synergy Effect of deformation and high temperature oxidation resistance

Pending Publication Date: 2019-08-09
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Zirconium alloys react violently with water vapor at high temperatures, and when the temperature exceeds 1200°C, a large amount of hydrogen and heat are released, which brings great safety hazards

Method used

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  • Coating layer for high-efficient combination of nuclear reactor and preparation method of coating layer
  • Coating layer for high-efficient combination of nuclear reactor and preparation method of coating layer

Examples

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Effect test

Embodiment 1

[0044] In this embodiment, the following preparation method is used to coat the Zr-Cr / Cr cladding layer on the outer surface of the Zr-4 alloy tube, and the specific operation steps are:

[0045] Setp1, Zr-4 alloy substrate outer surface pretreatment:

[0046] Use the Zr-4 finished tube that meets the technical specifications of the reactor cladding material, first perform ultrasonic cleaning with acetone solution for 30 minutes, then rinse with deionized water in large quantities, and then put it in a special high-vacuum drying room and dry it at 110°C for 30 minutes .

[0047] Setp2, ion cleaning of Zr-4 alloy substrate surface before deposition:

[0048] Put the dried Zr-4 alloy matrix into the furnace cavity, the base distance of the target in the furnace cavity is 100mm, and vacuumize to 3.0×10 -3 After Pa, start heating to 350°C, then fill in an appropriate amount of Ar gas to make the pressure reach 0.5Pa, adjust the duty cycle to 50%, and apply a high bias voltage of -...

Embodiment 2

[0058] In this embodiment, the following preparation method is used to coat the outer surface of the Zr-4 alloy tube with a Ti-Cr / Cr cladding layer, and the specific operation steps are:

[0059] Setp1, Zr-4 alloy substrate outer surface pretreatment:

[0060] Use the Zr-4 finished tube that meets the technical specifications of the reactor cladding material, first perform ultrasonic cleaning with acetone solution for 30 minutes, then rinse with deionized water in large quantities, and then put it in a special high-vacuum drying room and dry it at 120°C for 30 minutes .

[0061] Setp2, ion cleaning of Zr-4 alloy substrate surface before deposition:

[0062] Put the dried Zr-4 alloy into the furnace chamber, the base distance of the furnace chamber target is 120mm, and vacuumize to 5.0×10 -3 After Pa, start heating to 450°C, then fill in an appropriate amount of Ar gas to make the air pressure reach 2Pa, the high bias voltage is -200V, the current of the bunching coil is 8A, ...

Embodiment 3

[0072] In this embodiment, the following preparation method is used to coat the outer surface of the N36 alloy tube with a Zr-Cr / Cr cladding layer, and the specific operation steps are:

[0073] Setp1, N36 alloy substrate outer surface pretreatment:

[0074] N36 finished tubes that meet the technical specifications of the reactor cladding materials were used, first cleaned by ultrasonic cleaning with acetone solution for 30 minutes, then rinsed with deionized water in large quantities, and then dried in a special high-vacuum drying room at 110°C for 3 minutes.

[0075] Setp2, ion cleaning of N36 alloy substrate surface before deposition:

[0076] Put the dried N36 alloy substrate into the furnace cavity, the target base distance of the furnace cavity is 100mm, and vacuumize to 3.0×10 -3 After Pa, start heating to 350°C, then fill in an appropriate amount of Ar gas to make the pressure reach 0.5Pa, adjust the duty cycle to 50%, and apply a high bias voltage of -500V to -900V f...

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Abstract

The invention discloses a coating layer for high-efficient combination of a nuclear reactor. The coating layer is deposited on the external surface of matix materials used for the nuclear reactor, andthe coating layer successively includes a Zr-Cr or Ti-Cr transition layer and a Cr deposition layer from internal to external; the preparation method of the coating layer adopts a physical vapor deposition method, a thermal spraying method, a cooling spraying method, a laser cladding method, an electrochemical plating or a chemical vapor deposition method, and preferably adopts an arc ion platingof the physical vapor deposition method. According to the coating layer, zirconium alloy matrix materials are coated with the coating layer to obtain cladding materials with good ability of corrosionresistance, membrane-matrix cooperative deformation and high temperature and oxidation resistance; and the cladding materials are accident resistance fuel cladding materials with a promising development prospect, and high-temperature mechanical properties of coated cladding materials taking N36 as a matrix are better.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor materials, in particular to a high-efficiency bonding cladding layer for nuclear reactors and a preparation method thereof. Background technique [0002] As the cladding material of light water reactor, zirconium alloy shows good radiation resistance and corrosion resistance, and has been successfully used in nuclear power plant pressurized water reactor for decades. Zirconium alloys react violently with water vapor at high temperatures, and when the temperature exceeds 1200°C, a large amount of hydrogen and heat are released, which brings great safety hazards. How to further improve the safety and reliability of light water reactor nuclear fuel elements under accident conditions has become an urgent problem to be solved by nuclear science researchers. Therefore, reactor design puts forward higher safety margin requirements for fuel performance. A breakthrough in the challenge of reactor ...

Claims

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Application Information

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IPC IPC(8): C23C14/02C23C14/16C23C14/32
CPCC23C14/022C23C14/16C23C14/325
Inventor 张瑞谦杨红艳邱绍宇王昱杜沛南韦天国陈寰
Owner NUCLEAR POWER INSTITUTE OF CHINA
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