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Grant: Collaborative Research and Development Grants

Royal Military College of Canada

$130,000.00

Advanced computational modelling for the development of nuclear reactor materials

EF 2013-14

Résumé
This proposal recommends that the thermodynamic expertise of the principal investigator, Dr. Emily Corcoran and the funding and support of COG, UNENE and CFM be leveraged to assist and enhance the understanding and development of nuclear reactor materials while nurturing and encouraging willing talent in support of the Canadian Nuclear industry initiatives. Three separate projects, which are of interest to the nuclear industry, are proposed. Namely: 1) Thermodynamic modelling of alternative Be-replacement brazing materials will assist the nuclear industry to identify of the best alternative material that could replace, the potentially toxic, beryllium braze utilized currently;2) Computational modelling of stress corrosion cracking mitigation techniques for nuclear fuel bundles, will lead to an improved understanding of SCC phenomenon, which could assist the industry to determine alternative mitigation strategies and improve operational margins; and3) Developing a Molybdenum (Mo)-based oxygen sensor for nuclear fuel will improve knowledge of the behavior of the Mo fission product in the nuclear fuel as a function of oxygen partial pressure. Data, as a function of oxygen partial pressure, will be gathered on the phase portion of Mo in the metal and oxide phases, the solubility MoO2 in the UO2+x phase, the non-stoichiometry of MoO2 phase and the formation of UMoO6. This data will assist in developing a forensic methodology for determining the local oxygen partial pressure in high burnup nuclear fuel, which has applications in post irradiation examination of defective fuel and advanced fuel. This data will also assist in the development of our Canadian thermodynamic nuclear fuel model.
Programme
Collaborative Research and Development Grants
Emplacement
Ontario, Canada
Type de bénéficiaire
Academia
Type
Grant
Source
NSERC's Awards Data

Tel que publié

Application id
428829-2011
Name nom
Corcoran, Emily
Department département
Chemistry and Chemical Engineering
Organization id
30
Institution établissement
Royal Military College of Canada
Province en
Ontario
Province fr
Ontario
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2013
Competition year année de concours
2011
Award amount
130000
Program id
CRDPJ
Program name en
Collaborative Research and Development Grants
Program name fr
Subventions de recherche et développement coopérative
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
2400
Research subject group en
Nuclear engineering
Research subject group fr
Génie nucléaire
Research subject en
Nuclear engineering
Research subject fr
Génie nucléaire
Partie
2
Nb partie
5
Application title
Advanced computational modelling for the development of nuclear reactor materials
Keyword
NSERC
Application summary
This proposal recommends that the thermodynamic expertise of the principal investigator, Dr. Emily Corcoran and the funding and support of COG, UNENE and CFM be leveraged to assist and enhance the understanding and development of nuclear reactor materials while nurturing and encouraging willing talent in support of the Canadian Nuclear industry initiatives. Three separate projects, which are of interest to the nuclear industry, are proposed. Namely: 1) Thermodynamic modelling of alternative Be-replacement brazing materials will assist the nuclear industry to identify of the best alternative material that could replace, the potentially toxic, beryllium braze utilized currently;2) Computational modelling of stress corrosion cracking mitigation techniques for nuclear fuel bundles, will lead to an improved understanding of SCC phenomenon, which could assist the industry to determine alternative mitigation strategies and improve operational margins; and3) Developing a Molybdenum (Mo)-based oxygen sensor for nuclear fuel will improve knowledge of the behavior of the Mo fission product in the nuclear fuel as a function of oxygen partial pressure. Data, as a function of oxygen partial pressure, will be gathered on the phase portion of Mo in the metal and oxide phases, the solubility MoO2 in the UO2+x phase, the non-stoichiometry of MoO2 phase and the formation of UMoO6. This data will assist in developing a forensic methodology for determining the local oxygen partial pressure in high burnup nuclear fuel, which has applications in post irradiation examination of defective fuel and advanced fuel. This data will also assist in the development of our Canadian thermodynamic nuclear fuel model.