Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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CORROSION BEHAVIOR OF AUSTENITIC AND FERRITIC STEELS IN SUPERCRITICAL WATER

  • Luo, Xin (National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Tang, Rui (National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Long, Chongsheng (National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Miao, Zhi (National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Peng, Qian (National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China) ;
  • Li, Cong (China Nuclear Power Technology Research Institute)
  • Published : 2008.03.31
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Abstract

The general corrosion behavior of austenitic and ferritic steels(316L, 304, N controlled 304L, and 410) in supercritical water is investigated in this paper. After exposure to deaerated supercritical water at $480^{\circ}C$/25 MPa for up to 500 h, the four steels studied were characterized using gravimetry, scanning electron microscopy/energy dispersive X-ray spectroscopy(SEM/EDS), X-ray photoelectron spectroscopy(XPS), and X-ray diffraction(XRD). The results show that the 316L steel with a higher Cr and Ni content has the best corrosion-resistance performance among the steels tested. In addition to the oxide layer mixed with $Fe_{3}O_{4}$ and $(Fe,Cr)_{3}O_{4}$ that formed on all the samples, a $Fe_{3}O_{4}$ loose outer layer was observed on the 410 steel. The corrosion mechanism of stainless steels in supercritical water is discussed based on the above results.

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