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

Suzan Bsat (Corresponding Author), Xiao Huang, Sami Penttilä

Research output: Contribution to journalArticleScientificpeer-review

1 Citation (Scopus)

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 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 Cr 2O 3 with spinel (Ni(Cr, Al) 2O 4), was observed on NiCrAlY surface after 1000 h in SCW.

Original languageEnglish
Article number011017
Pages (from-to)377-389
JournalJournal of Nuclear Engineering and Radiation Science
Volume4
Issue number1
DOIs
Publication statusPublished - 2017
MoE publication typeA1 Journal article-refereed
Event8th International Symposium on Super-Critical Water-cooled Reactors, ISSCWR-8 - Chengdu, China
Duration: 13 Mar 201715 Mar 2017

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corrosion
water cooled reactors
Water cooled reactors
Corrosion
water
Water
thermodynamic efficiency
fossil fuels
Oxides
oxides
greenhouses
coolants
nuclear energy
simplification
Gas emissions
Canada
Fossil fuels
Greenhouse gases
Nuclear energy
Coolants

Cite this

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title = "Corrosion behaviour of bare and NiCrAlY coated alloy 214 in SCW at 700C",
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 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 Cr 2O 3 with spinel (Ni(Cr, Al) 2O 4), was observed on NiCrAlY surface after 1000 h in SCW.",
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Corrosion behaviour of bare and NiCrAlY coated alloy 214 in SCW at 700C. / Bsat, Suzan (Corresponding Author); Huang, Xiao; Penttilä, Sami.

In: Journal of Nuclear Engineering and Radiation Science, Vol. 4, No. 1, 011017, 2017, p. 377-389.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

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AU - Huang, Xiao

AU - Penttilä, Sami

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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 Cr 2O 3 with spinel (Ni(Cr, Al) 2O 4), was observed on NiCrAlY surface after 1000 h in SCW.

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