TY - JOUR
T1 - Corrosion behaviour of bare and NiCrAlY coated alloy 214 in SCW at 700°C
AU - Bsat, Suzan
AU - Huang, Xiao
AU - Penttilä, Sami
N1 - Funding Information:
Funding to the Canada Gen-IV National Program was provided by Natural Resources Canada through the Office of Energy Research and Development, Atomic Energy of Canada Limited, and Natural Sciences and Engineering Research Council of Canada as well as Academy of Finland project IDEA (Interactive Modelling of Fuel Cladding Degradation Mechanisms) is gratefully acknowledged.
Publisher Copyright:
Copyright © 2018 by ASME.
Copyright:
Copyright 2019 Elsevier B.V., All rights reserved.
PY - 2017
Y1 - 2017
N2 - 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 behaviors of bare alloy 214 and NiCrAlY coated 214 under SCW at a temperature of 700°C/25 MPa for 1000 h. The results show that chromium and nickel based oxide forms on the bare surface after exposure in SCW for 1000 h. A dense and adhered oxide layer, consisting of Cr2O3 with spinel (Ni(Cr, Al)2O4), was observed on NiCrAlY surface after 1000 h in SCW.
AB - 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 behaviors of bare alloy 214 and NiCrAlY coated 214 under SCW at a temperature of 700°C/25 MPa for 1000 h. The results show that chromium and nickel based oxide forms on the bare surface after exposure in SCW for 1000 h. A dense and adhered oxide layer, consisting of Cr2O3 with spinel (Ni(Cr, Al)2O4), was observed on NiCrAlY surface after 1000 h in SCW.
UR - http://www.scopus.com/inward/record.url?scp=85046298734&partnerID=8YFLogxK
U2 - 10.1115/1.4037324
DO - 10.1115/1.4037324
M3 - Article
SN - 2332-8983
VL - 4
SP - 377
EP - 389
JO - Journal of Nuclear Engineering and Radiation Science
JF - Journal of Nuclear Engineering and Radiation Science
IS - 1
M1 - 011017
T2 - 8th International Symposium on Super-Critical Water-cooled Reactors, ISSCWR-8
Y2 - 13 March 2017 through 15 March 2017
ER -