Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for SCWR in superheated steam. Abe, H., Hong, S. M., & Watanabe, Y. Nuclear Engineering and Design, 280:652–660, December, 2014. WOS:000347265100064
doi  abstract   bibtex   
Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for supercritical-water-cooled reactor (SCWR), including three types of 15Cr-20Ni stainless steels (1520 SSs), in the temperature range of 700-780 degrees C superheated steam have been investigated. Effect of temperature, dissolved oxygen (DO), degree of cold work (CW), and machined layer by cold drawing process on the oxidation kinetics assuming power-law kinetics are discussed. Characteristics of oxide layers and its relation to oxidation behaviors are also discussed. The effect of DO on the weight gain behavior in superheated steam at 700 degrees C was minor for all specimens at least up to 200 ppb DO. The tube-shaped specimens of 1520 SSs showed very good oxidation resistance at 700-780 degrees C. There was no clear difference in the oxidation kinetics among the three investigated types of 1520 SSs. The machined layer formed at the tube surface has a significant role to mitigate oxidation in superheated steam. A fine-grained microstructure near the surface due to recrystallization by cold drawing process is effective to form the protective Cr2O3 layer. It has been suggested that since Cr diffusion in the outside surface of tubes is accelerated as a result of an increased dislocation density and/or grain refinement by cold drawing, tube specimens show very slow oxidation kinetics. Breakdown of the protective Cr2O3 layer and nodule oxide formation were partly observed on the tube-shaped specimens of 15Cr-20Ni SSs. The reliability of Cr2O3 layer has to be carefully examined to predict the oxidation kinetics after long-term exposure. (C) 2014 Elsevier B.V. All rights reserved.
@article{abe_oxidation_2014,
	title = {Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for {SCWR} in superheated steam},
	volume = {280},
	issn = {0029-5493},
	doi = {10.1016/j.nucengdes.2014.08.020},
	abstract = {Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for supercritical-water-cooled reactor (SCWR), including three types of 15Cr-20Ni stainless steels (1520 SSs), in the temperature range of 700-780 degrees C superheated steam have been investigated. Effect of temperature, dissolved oxygen (DO), degree of cold work (CW), and machined layer by cold drawing process on the oxidation kinetics assuming power-law kinetics are discussed. Characteristics of oxide layers and its relation to oxidation behaviors are also discussed. The effect of DO on the weight gain behavior in superheated steam at 700 degrees C was minor for all specimens at least up to 200 ppb DO. The tube-shaped specimens of 1520 SSs showed very good oxidation resistance at 700-780 degrees C. There was no clear difference in the oxidation kinetics among the three investigated types of 1520 SSs. The machined layer formed at the tube surface has a significant role to mitigate oxidation in superheated steam. A fine-grained microstructure near the surface due to recrystallization by cold drawing process is effective to form the protective Cr2O3 layer. It has been suggested that since Cr diffusion in the outside surface of tubes is accelerated as a result of an increased dislocation density and/or grain refinement by cold drawing, tube specimens show very slow oxidation kinetics. Breakdown of the protective Cr2O3 layer and nodule oxide formation were partly observed on the tube-shaped specimens of 15Cr-20Ni SSs. The reliability of Cr2O3 layer has to be carefully examined to predict the oxidation kinetics after long-term exposure. (C) 2014 Elsevier B.V. All rights reserved.},
	language = {English},
	journal = {Nuclear Engineering and Design},
	author = {Abe, Hiroshi and Hong, Seung Mo and Watanabe, Yutaka},
	month = dec,
	year = {2014},
	note = {WOS:000347265100064},
	keywords = {alloys, corrosion behavior, high-temperature steam, resistance, stress-corrosion, supercritical water, t91, vapor},
	pages = {652--660}
}

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