Performance of Chemical Vapor Deposition and Plasma Spray-Coated Stainless Steel 310 in Supercritical Water-Reference-Cited by-同舟云学术

Performance of Chemical Vapor Deposition and Plasma Spray-Coated Stainless Steel 310 in Supercritical Water

Published:2016-02-29 Issue:2 Volume:2 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

Huang Xiao¹,Yang Q.²,Guzonas Dave³

Affiliation:

1. Mechanical and Aerospace Engineering Department, Carleton University, 1125 Colonel By Dr., Ottawa, ON K1S 5B6, Canada e-mail:

2. National Research Council Canada, Ottawa, ON K1A 0R6, Canada

3. Atomic Energy of Canada Limited, Chalk River, ON K0J 1J0, Canada

Abstract

In this study, aluminized and NiCrAlY plasma-sprayed AISI 310 stainless steel samples were tested in supercritical water (SCW) at 500°C. The microstructure after SCW exposure was analyzed using scanning electron microscopy (SEM), energy-dispersive spectroscopy (EDS), and X-ray diffraction (XRD). Weight measurements were taken before and after exposure to provide quantitative comparison of the two coatings on AISI 310 base metal. The results showed that aluminized and bare 310 stainless steel experienced similar weight gain, in the range of 0.02–0.08 mg/cm2 after 1550 hr. The aluminized sample had a slight weight decrease as exposure progressed. Oxide formation, in the forms of Al2O3 and (Fe,Cr)2O3, was found on the aluminized surface along with surface cracking after 1550 hr testing in SCW. NiCrAlY-coated 310, however, had the most consistent weight increase and oxide formation (mainly Al2O3) on the surface. Based on the results from this study, the aluminized coating has limitations in providing surface protection due to surface cracking and weight loss. The NiCrAlY plasma-sprayed coating with alumina formation on the surface has the potential to provide long-term surface protection to the substrate material in SCW.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4031198/6066714/ners_2_2_021011.pdf

Reference21 articles.

1. Generation IV Advanced Nuclear Energy Systems;Nucl. Plant J.,2008

2. Khartabil, H., 2009 “SCWR: Overview,” GIF Symposium, Paris, France, September, GIF, Paris, France.

3. Leung, L., 2012, “Canada’s Super-Critical Water-Cooled Reactor Design Concept,” Phase-II NSERC/NRCan/AECL Gen-IV Energy, Technologies Program Kick-Off Meeting, Saskatoon, Canada, June 14, Atomic Energy Canada Laboratory, Chalk River, ON.

4. Kaneda, J., Kasahara, S., Kuniya, J., Kano, F., Saito, N., Shioiri, A., Shibayama, T., and Takahashi, H., 2005, “General Corrosion Properties of Titanium Based Alloys for the Fuel Claddings in the Supercritical Water-Cooled Reactor,” Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System—Water Reactors, The Minerals, Metals & Materials Society, Salt Lake City, UT.

Cited by 6 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy;Molecules;2023-01-15

2. Corrosion Testing of CrNx-Coated 310 H Stainless Steel under Simulated Supercritical Water Conditions;Materials;2022-08-10

3. Oxidation Behavior of an Austenitic Steel (Fe, Cr and Ni), the 310 H, in a Deaerated Supercritical Water Static System;Metals;2021-04-01

4. Effects of temperature on corrosion performances of TiO2/SS316L in supercritical water for hydrogen production;International Journal of Hydrogen Energy;2019-09

5. Corrosion Behaviour of Bare and NiCrAlY Coated Alloy 214 in Supercritical Water at 700 °C;Journal of Nuclear Engineering and Radiation Science;2017-12-04