Grant: Strategic Projects - Group
University of Saskatchewan
$156,597.00
Safer fuel and cladding for future nuclear reactor
FY 2015-16
Summary
Recent tragic accident in Fukushima clearly demonstrates urgency of the design of safer nuclear fuel. The safety of uranium based reactors can be improved if thermal conductivity of the fuel is increased; this would lower the fuel temperature, prevent melting of the reactor core and the failure of fuel cladding. Higher thermal conductivity would also lower thermal stresses, prevent fuel cracking and increase its longevity. Generation IV reactors like Supercritical Water Cooled (SWC) Candu reactor, will have higher thermal efficiency and will be operating at higher temperatures and pressures and therefore development of novel materials for fuel cladding is critical. Our work will be focused on manufacturing novel high thermal conductivity composite fuel with spark plasma sintering, and testing materials for cladding that can operate at high temperatures. Combined experimental investigations and predictive simulations would allow us to make recommendations for nuclear materials for safer operation of SWR nuclear reactors.
Safety of energy production can be significantly improved when thorium reactors are build. There are however several important material-related problems that have to be solved. Candu Energy Inc., designer of thorium based Candu reactor, identified for us what physical and mechanical properties of thorium fuel at high temperature are not well known, and these properties are required for their design. We plan applying state of the art, first principle (predictive) modelling to obtain necessary data. New experimental techniques will be used, for the first time, to analyse structure and measure thermal characteristics at large range of temperatures, up to 2800°C. The dependence of thermal, and selected mechanical properties on microstructure will be studied in details.
Our comprehensive approach, combining ab-initio simulation with innovative experiments, will contribute to development of accident tolerant fuel and safer fuel cladding systems of future Candu reactors.
Program
Strategic Projects - Group
Recipient
Location
Saskatchewan, Canada
Recipient Type
Academia
Type
Grant
Source
NSERC's Awards Data
As published
Application id
479107-2015
Name nom
Szpunar, Jerzy
Department département
Mechanical Engineering
Organization id
16
Institution établissement
University of Saskatchewan
Province en
Saskatchewan
Province fr
Saskatchewan
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2015
Competition year année de concours
2015
Award amount
156597
Program id
STPGP
Program name en
Strategic Projects - Group
Program name fr
Projets stratégiques - De groupe
Group en
Research partnerships programs
Group fr
Programmes de partenariat
Committee code
1571
Committee name en
Strategic Projects Selection Panel - Energy
Committee name fr
Comité de sélection des projets stratégiques - Énergie
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
1
Nb partie
3
Application title
Safer fuel and cladding for future nuclear reactor
Keyword
NSERC
Application summary
Recent tragic accident in Fukushima clearly demonstrates urgency of the design of safer nuclear fuel. The safety of uranium based reactors can be improved if thermal conductivity of the fuel is increased; this would lower the fuel temperature, prevent melting of the reactor core and the failure of fuel cladding. Higher thermal conductivity would also lower thermal stresses, prevent fuel cracking and increase its longevity. Generation IV reactors like Supercritical Water Cooled (SWC) Candu reactor, will have higher thermal efficiency and will be operating at higher temperatures and pressures and therefore development of novel materials for fuel cladding is critical. Our work will be focused on manufacturing novel high thermal conductivity composite fuel with spark plasma sintering, and testing materials for cladding that can operate at high temperatures. Combined experimental investigations and predictive simulations would allow us to make recommendations for nuclear materials for safer operation of SWR nuclear reactors.
Safety of energy production can be significantly improved when thorium reactors are build. There are however several important material-related problems that have to be solved. Candu Energy Inc., designer of thorium based Candu reactor, identified for us what physical and mechanical properties of thorium fuel at high temperature are not well known, and these properties are required for their design. We plan applying state of the art, first principle (predictive) modelling to obtain necessary data. New experimental techniques will be used, for the first time, to analyse structure and measure thermal characteristics at large range of temperatures, up to 2800°C. The dependence of thermal, and selected mechanical properties on microstructure will be studied in details.
Our comprehensive approach, combining ab-initio simulation with innovative experiments, will contribute to development of accident tolerant fuel and safer fuel cladding systems of future Candu reactors.