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Corrosion Behaviors of Candidate Materials for Supercritical Water-cooled Reactor

Author: ZhuFaWen
Tutor: ZhangLeFu
School: Shanghai Jiaotong University
Course: Nuclear Energy Science and Engineering
Keywords: Supercritical water cooled reactor Corrosion Resistance Oxide film Corrosion mechanism
CLC: TL34
Type: Master's thesis
Year: 2010
Downloads: 246
Quote: 2
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Abstract


Supercritical water cooled reactor (SCWR) is a fourth-generation reactors only six concept heap type water cooled reactors, the many advantages of the economy, the continuity and sustainability, the main type of reactor is suitable for large-scale power generation. SCWR reactor core outlet temperature up to 500 ~ 650 ℃, the corrosion of metallic materials is extremely serious, the existing fuel cladding material for pressurized water reactor nuclear power plants may no longer apply. Preliminary screening assessment used in super critical thermal power plants and the PWR fuel assemblies and high temperature environment such material, made a series of supercritical water cooled reactor candidate materials, including ferritic / martensitic (F / M ) steel, austenitic stainless steel, nickel base alloy and oxide dispersion strengthened the Steel (ODS). The study of these candidate materials in supercritical water corrosion behavior of people to find suitable reactor components and fuel cladding material of vital significance. P92, 304NG, AL-6XN, C276 and MA956 candidate materials at a temperature of 550,600,650 ℃, pressure of 25MPa supercritical water static and dynamic corrosion tests, the experimental time is 1000 hours. Using optical microscopy, scanning electron microscopy (SEM), X-ray energy dispersive spectroscopy (EDS) and X-ray diffractometer (XRD) analysis of the surface morphology of the oxide film of each candidate materials, microstructure and elemental composition distribution. Experiments show that, the lower Cr content of the ferritic / martensitic steels P92 having a high corrosion rate, Cr, high content of Ni austenitic stainless steels AL-6XN 304NG has a lower corrosion rate, Cr, Ni, nickel base alloy with high Mo content C276 has a lower corrosion rate, containing higher CR Al element oxide dispersion strengthened steel MA956 has a very low corrosion rate. F / M steel and austenitic stainless steel surface oxide film is generally a two-tier structure, the outer layer is a Fe-rich magnetic spar structure, the inner layer is a Cr-rich spinel structure. P92 steel surface oxide film at 600 ℃ cracking 304NG stainless steel surface of the nodular corrosion, the corrosion product particles AL-6XN surface forming a magneto spar structure, and very thin, stable oxide film is formed in C276 and MA956 , but the surface of the presence of pitting and shedding phenomenon. The experiments show that the static corrosion of temperature on the corrosion of the material weight gain a great influence on the corrosion weight gain of all of the candidate materials at 600 ℃ most serious; dynamic water corrosion, the temperature only 304NG stainless steel corrosion weight gain significantly affected, little effect on other materials. At the same temperature, the corrosion weight gain of the material in the dynamic water than the significant increase in the static water, indicating that the flow of water to accelerate the corrosion of the material. In short, on the material surface to form a dense, complete and stable protective oxide film is extremely critical for the material to resist the supercritical water corrosion. Cr, Al element is a key element, but stability of the oxide film formed of a material in a supercritical environment easily volatile corrosion product is formed, resulting in partial loss of the oxide film leaving the protective role of the corrosion speed. According to the results of the experimental screening MA956, C276, AL-6XN three kinds of candidate materials in supercritical environment more excellent corrosion resistance, might as reactor components and cladding materials to be applied in the supercritical water-cooled heap.

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