Grant: NSERC/NRCan/AECL Generation IV Energy Technologies Program
Carleton University
$80,000.00
Effect of Long Term Exposure in Super-Critical Water and High Temperature Steam on Corrosion Behavior, Microstructure Stability, and Mechanical Properties of Coated Alloy(s)
EF 2014-15
Résumé
Concerns with green house gas emissions and uncertainty in the long-term supply of fossil fuels have resultedin renewed interest in nuclear energy as an essential part of the energy mix for the future. Currently, there is aworldwide effort to develop advanced Generation-IV nuclear reactor technologies with enhanced efficienciesand reduced operating cost. Canada is playing a lead role in the design of the Supercritical Water-CooledReactor (SCWR) - one of six reactor designs being considered by the Gen-IV International Forum (GIF). TheSCWR design will use supercritical water as coolant in order to achieve high thermodynamic efficiency (i.e.,over 45% vs. 33% for current reactors) and plant simplification. One of the major challenges for thedevelopment of the SCWR is the long-term stability of the materials in contact with the coolant. In thisresearch, the effect of long term exposure in super-critical water (500- 850°C) on corrosion behaviour,microstructure, and mechanical properties of coated and uncoated candidate substrate alloy(s) for use in aSCWR will be examined. FeCrAlY or NiCrAlY based plasma spray coating and aluminide based diffusioncoating processes (all developed in phase one of the program) will be employed to provide improvement to thecorrosion resistance and microstructure stability of the selected substrate alloy. After SCW exposure, thecorrosion behaviour and microstructure changes will be analyzed. For the most promising coating andsubstrate system in terms of corrosion resistance and microstructure stability, high temperature mechanicalproperty tests will be carried out to elucidate what influence the coating may have on the mechanical integrityof the structural components for SCWR. The new knowledge and expertise generated from this research willhelp strengthen Canada's nuclear industry, particularly in the development and commercialization of SCWR.This research will help fulfil Canada's commitments to the SCWR Materials and Chemistry ProjectArrangement under the Framework Agreement for International Collaboration on Research and Developmentof Gen IV Nuclear Energy Systems.
Programme
NSERC/NRCan/AECL Generation IV Energy Technologies Program
Bénéficiaire
Emplacement
Ontario, Canada
Type de bénéficiaire
Academia
Type
Grant
Source
NSERC's Awards Data
Tel que publié
Application id
424204-2011
Name nom
Huang, Xiao
Department département
Mechanical & Aerospace Engineering
Organization id
23
Institution établissement
Carleton University
Province en
Ontario
Province fr
Ontario
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2014
Competition year année de concours
2011
Award amount
80000
Program id
NNAPJ
Program name en
NSERC/NRCan/AECL Generation IV Energy Technologies Program
Program name fr
Programme des technologies énergétiques de quatrième génération CRSNG RNCan EACL
Group en
Research partnerships programs
Group fr
Programmes de partenariat
Committee code
96
Committee name en
RPP Internal Decision Cttee
Committee name fr
Cté de décision interne - PPR
Area of application code
302
Area of application group en
Energy resources
Area of application group fr
Ressources d'énergie
Area of application en
Nuclear energy
Area of application fr
Énergie nucléaire
Research subject code
2001
Research subject group en
Materials science and technology
Research subject group fr
Science et technologie des matériaux
Research subject en
Materials structure, properties and testing
Research subject fr
Structure, propriétés et essais des matériaux
Partie
4
Nb partie
4
Application title
Effect of Long Term Exposure in Super-Critical Water and High Temperature Steam on Corrosion Behavior, Microstructure Stability, and Mechanical Properties of Coated Alloy(s)
Keyword
NSERC
Application summary
Concerns with green house gas emissions and uncertainty in the long-term supply of fossil fuels have resultedin renewed interest in nuclear energy as an essential part of the energy mix for the future. Currently, there is aworldwide effort to develop advanced Generation-IV nuclear reactor technologies with enhanced efficienciesand reduced operating cost. Canada is playing a lead role in the design of the Supercritical Water-CooledReactor (SCWR) - one of six reactor designs being considered by the Gen-IV International Forum (GIF). TheSCWR design will use supercritical water as coolant in order to achieve high thermodynamic efficiency (i.e.,over 45% vs. 33% for current reactors) and plant simplification. One of the major challenges for thedevelopment of the SCWR is the long-term stability of the materials in contact with the coolant. In thisresearch, the effect of long term exposure in super-critical water (500- 850°C) on corrosion behaviour,microstructure, and mechanical properties of coated and uncoated candidate substrate alloy(s) for use in aSCWR will be examined. FeCrAlY or NiCrAlY based plasma spray coating and aluminide based diffusioncoating processes (all developed in phase one of the program) will be employed to provide improvement to thecorrosion resistance and microstructure stability of the selected substrate alloy. After SCW exposure, thecorrosion behaviour and microstructure changes will be analyzed. For the most promising coating andsubstrate system in terms of corrosion resistance and microstructure stability, high temperature mechanicalproperty tests will be carried out to elucidate what influence the coating may have on the mechanical integrityof the structural components for SCWR. The new knowledge and expertise generated from this research willhelp strengthen Canada's nuclear industry, particularly in the development and commercialization of SCWR.This research will help fulfil Canada's commitments to the SCWR Materials and Chemistry ProjectArrangement under the Framework Agreement for International Collaboration on Research and Developmentof Gen IV Nuclear Energy Systems.