Anti-vibration alloy material for nuclear power station steam generator and preparation process thereof

Abstract

The invention discloses an anti-vibration alloy material for a nuclear power station steam generator. The anti-vibration alloy material is used for fabricating anti-vibration strips, retaining rings and retaining strips of nuclear power station steam generators and comprises the following components by weight percent: C 0.015 to 0.030%, Si 0.05 to 0.5%, Mn 0.05 to 0.50%, P <= 0.015%, S <= 0.010%, Cr 28.0 to 31.0%, Ni 58.0 to 63%, Cu 0.001 to 0.20%, Ti 0.005 to 0.5%, Al 0.005 to 0.5%, Fe 7.0 to 11.0%, Re 0.01 to 1.0%, Nb 0.001 to 0.10% and Mo 0.001 to 0.10%, with the balance being unavoidable impurities. A preparation process for the material comprises the following steps: A, preparation of raw materials according to weight percent of the components of the anti-vibration alloy material; B, cleaning and drying of the surfaces of the prepared raw materials and high vacuum smelting of the raw materials in a vacuum smelting furnace according to a melting order; C, re-melting and refining of electroslag; D, forging; E, hot rolling; F, vacuum solid solution heat treatment; G, surface processing of bars; and H, multi-pass drawing, annealing, drawing and linear cutting. A finished product of the anti-vibration material is obtained after the above-mentioned steps; design of the components of the material is reasonable, and the preparation process is advanced.

Description

technical field [0001] The invention relates to an anti-vibration material in the technical field of new materials, in particular to an anti-vibration alloy material for a steam generator in a nuclear power plant and a preparation method thereof. strip material. Background technique [0002] AP1000 is the third-generation advanced pressurized water reactor nuclear power unit developed by Westinghouse Corporation. The main feature that distinguishes AP1000 from the second generation plus CPR1000 pressurized water reactor nuclear power unit is the "passive" safety system. The "passive" design concept is to use the inherent thermal-hydraulic characteristics to simplify the design of the safety system, so that the safety measures of the nuclear power plant no longer rely on the operation of active equipment such as pumps and fans, thereby greatly reducing the number of safety-level valves, Pumps, cables and anti-seismic workshops; class 1E emergency diesel generator system is ...

AI Technical Summary

Problems solved by technology

The operating experience of nuclear power plants shows that the heat transfer tube is the most critical and weakest link in the pressure boundary of the loop system. Once the heat transfer tube is damaged by v

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