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research-article

Corrosion behaviour of bare and NiCrAlY coated Alloy 214 in SCW at 700?C

[+] Author and Article Information
Bsat Suzan

Carleton University, 1125 Colonel by Drive, Ottawa, ON, Canada, K1S5B6
suzan.bsat@carleton.ca

Huang Xiao

Carleton University, 1125 Colonel by Drive, Ottawa, ON, Canada, K1S5B6
xiao.huang@carleton.ca

Penttila Sami

VTT Technical Research of Finland Ltd., Vuorimiehentie 3, 02150 Espoo, Finland
sami.penttila@vtt.fi

1Corresponding author.

ASME doi:10.1115/1.4037324 History: Received April 24, 2017; Revised July 04, 2017

Abstract

Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have resulted in renewed interest in nuclear energy as an essential part of the energy mix for the future. Many countries worldwide including Canada, China and EU are currently undertaking the design of Generation IV supercritical water-cooled reactor (SCWR) with higher thermodynamic efficiency and considerable plant simplification. The identification of appropriate materials for in-core and out-of-core components to contain the supercritical water (SCW) coolant is one of the major challenges for the design of SCWR. This study is carried out to evaluate the oxidation/corrosion behaviours of bare Alloy 214 and NiCrAlY coated 214 under SCW at a temperature of 700°C/25MPa for 1000 hours. The results show that chromium and nickel based oxide forms on the bare surface after exposure in SCW for 1000 hours. A dense and adhered oxide layer, consisting of Cr2O3 with spinel (Ni(Cr, Al)2O4), was observed on NiCrAlY surface after 1000 hours in SCW.

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