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Investigation on Flow Accelerated Corrosion of Carbon Steels for Pwr Secondary Piping

Author: YiChengLong
Tutor: ZhangLeFu
School: Shanghai Jiaotong University
Course: Nuclear Energy Science and Engineering
Keywords: Flow accelerated corrosion Nuclear power plant P11 Two - loop piping Saturated vapor Shear force
CLC: TL334
Type: Master's thesis
Year: 2012
Downloads: 53
Quote: 0
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Abstract


PWR nuclear power plant in order to protect the steam generator (SG), second circuit water quality requirements for the high pH and low dissolved oxygen, while the two-loop carbon steel pipeline in this condition is prone to flow accelerated corrosion. (Flowacceleratedcorrosion, FAC) for carbon or low alloy steel pipe wall thinning phenomenon occurs in the water or vapor-liquid two-phase flow of single-phase flow accelerated corrosion. The purpose of this study is that the Cr content of the three-carbon steel piping material corrosion at high flow rates of saturated steam conditions FAC curve to the low cost of experiments. The study used both tubular and sheet specimens: diameter above Φ2mm the tubular and Φ9mm sheet sample. Experimental temperature of 273 ° C, pressure of 5.8MPa, flow of 20kg / h, heating power of about 24kW. Tube saturated steam flow rate of up to 60m / s, pH value, dissolved oxygen and other water chemistry parameters controllable. The corrosion weighing and scanning electron microscopy (SEM) the erosion after SA106B-0Cr, SA106B-0.2Cr and a the SA335-P11 analysis while using Ansys CFD CFX simulation of the test section, perforated plate straight pipe and elbow . The experimental and simulation results show that the lower P11 flaky corrosion rate of the sample in the high-speed wet steam, the surface oxide film is not complete, a message stating that the the pearlite priority corrosion phenomenon. And SA1060B-0Cr SA1060B-0.2Cr samples show more pits, with the chloride ion in water containing trace. P11 tubular specimens inlet section appears obvious the FAC corrosion morphology, weaker specimens middle, end almost disappeared, the temperature drop of the test section and dryness decreased tubular experimental results to estimate the degree of the P11 steel FAC critical stem is about 92%. P11 the flaky sample under erosion at high speed with the dryness and the flow rate of decline, the corrosion rate decreased and the highest annual thinning rate of less than 0.16mm. Different diameter, orifice diameter and flow rate on the orifice pipeline downstream. The same diameter, the smaller the inner diameter of the orifice plate, the greater downstream peak maxima points away from the orifice plate position. Orifice plate downstream doubled in diameter to twice the diameter between the shear stress maxima, FAC hazardous areas should focus on examination of the nuclear power plant overhaul period. Flake scour when the shear force of the surface of the sample increases as the angle increases, the erosion angle for Sample FAC great influence. 90 ° scouring the surface of the specimen form scouring ring, distribution in good agreement with the experimental results.

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CLC: > Industrial Technology > Nuclear technology > Engineering of Nuclear Reactors > Reactor thermal hydraulics design, calculation > Reactor hydrodynamics
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