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Grant: NSERC/NRCan/AECL Generation IV Energy Technologies Program

Carleton University

$3,995.00

Corrosion Resistant Coatings for SCWR Coolant-Contacting Components

EF 2011-12

Résumé
Concerns with green house gas emissions and the uncertainty in the 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. Currently, there is a worldwide effort to develop advanced Generation-IV nuclear reactor technologies with enhanced efficiencies and reduced operating cost. Canada is taking the lead role in the design of the Supercritical Water-Cooled Reactor (SCWR) - one of six reactor designs being considered by the Gen-IV International Forum (GIF). The SCWR design will use supercritical water as coolant in order to achieve high thermodynamic efficiency (i.e., about 45% vs. 33% for current reactors) and plant simplification. In-core coolant will be contained in pressure tubes, in a similar way as in current CANDU designs. One of the major challenges for the development of the SCWR is the long-term stability of the materials in contact with the coolant. At present there is no single alloy that can meet all of the performance requirements in terms of corrosion resistance, mechanical properties, and stability under irradiation. Thus, development of suitable coatings for several key coolant-contacting components is needed. The proposed research will investigate coating compositions designed specifically for SCWR operating conditions, and several coating deposition processes. The outcome of this research is expected to generate new knowledge and expertise in coating development and contribute to the design and fabrication of the SCWR.
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
376333-2008
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
2011
Competition year année de concours
2008
Award amount
3995
Program id
NNAPJ
Program nane 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
300
Area of application group en
Energy resources
Area of application group fr
Ressources d'énergie
Area of application en
Energy resources (including production, exploration, processing, distribution and use)
Area of application fr
Ressources d'énergie (production, exploration, traitement, distribution et utilisation de l'énergie)
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
3
Nb partie
3
Application title
Corrosion Resistant Coatings for SCWR Coolant-Contacting Components
Keyword
NSERC
Application summary
Concerns with green house gas emissions and the uncertainty in the 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. Currently, there is a worldwide effort to develop advanced Generation-IV nuclear reactor technologies with enhanced efficiencies and reduced operating cost. Canada is taking the lead role in the design of the Supercritical Water-Cooled Reactor (SCWR) - one of six reactor designs being considered by the Gen-IV International Forum (GIF). The SCWR design will use supercritical water as coolant in order to achieve high thermodynamic efficiency (i.e., about 45% vs. 33% for current reactors) and plant simplification. In-core coolant will be contained in pressure tubes, in a similar way as in current CANDU designs. One of the major challenges for the development of the SCWR is the long-term stability of the materials in contact with the coolant. At present there is no single alloy that can meet all of the performance requirements in terms of corrosion resistance, mechanical properties, and stability under irradiation. Thus, development of suitable coatings for several key coolant-contacting components is needed. The proposed research will investigate coating compositions designed specifically for SCWR operating conditions, and several coating deposition processes. The outcome of this research is expected to generate new knowledge and expertise in coating development and contribute to the design and fabrication of the SCWR.