Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C

Author:

Tepylo Nick1,Huang Xiao1,Jiang Shengli1,Penttilä Sami2

Affiliation:

1. Department of Mechanical and Aerospace Engineering, Carleton University, 1125 Colonel By Drive, Ottawa, ON K1S 5B6, Canada

2. VTT Technical Research Centre of Finland Ltd., Espoo 02150, Finland

Abstract

The choice of materials is of great concern in the construction of Gen IV supercritical water reactors (SCWR), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. A material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, aluminide and Cr-modified aluminide coated 304, as well as bare stainless steel 304 as a reference material, were tested in supercritical water (SCW) at 700 °C and 25 MPa for 1000 h. The results showed that all three samples experienced weight loss. However, the aluminide coated 304 had 20 to 40 times less weight loss compared to Cr-modified aluminide coated and bare stainless steel 304 specimens, respectively. Based on scanning electron microscope/energy dispersive X-ray spectroscopy (SEM/EDS) and X-ray diffraction (XRD) analysis results, spinel and hematite Fe2O3 formed on bare 304 after 1000 h in SCW while alumina was observed on both coated specimens, i.e., aluminide and Cr-modified aluminide surfaces. Oxide spallation was observed on the bare 304 and Cr-modified aluminide surface, contributing to a larger weight loss. Based on the results from this study, pure aluminide coating with Al content of 10–11 wt % demonstrated superior performance than bare 304 and Cr-modified aluminide coated 304.

Funder

Natural Sciences and Engineering Research Council of Canada

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference47 articles.

1. World Population to 2300;United Nations Department of Economic and Social,2004

2. A Technology Roadmap for Generation IV Nuclear Energy System;U.S. DOE Nuclear Energy Research Advisory Committee and Gen IV International Forum (GIF),2002

3. Schulenberg, T., Matsui, H., Leung, L., and Sedov, A., 2012, “Supercritical Water Cooled Reactors,” GIF Symposium Proceedings and Annual Report, San Diego, CA.

4. Development and Integration of Canadian SCWR Concept With Counter-Flow Fuel Assembly,2013

5. Elevated Temperature Ferritic and Martensitic Steels and Their Application to Future Nuclear Reactors;Int. Mater. Rev.,2005

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