Grant: NSERC/NRCan/AECL Generation IV Energy Technologies Program
Carleton University
$80,000.00
Parametric Structural Design of GEN IV Canadian Super Critical Water Reactor (SCWR)
EF 2014-15
Résumé
A parametric solid mechanics model for the design of the reactor core of the GEN IV Canadian Supercritical Water Reactor (SCWR)will be developed to predict transient temperature, displacement, strain and stress fields in the reactor core in the early design stages. The model would be based on 3D transient FEM thermal-stress analysis for normal operation, startup, shut-down, upset and accident conditions. The model would be coupled to the best available estimates of fluid flow velocities, pressures, temperatures and densities. Temperature and if needed microstructure dependent properties would be used. The model would include non-linear contact elements for thermal and stress analysis based on the best available knowledge and if not available, sensitivity studies would be helpful, of the gap width, surface roughness, gap material of each contact interface.
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
424200-2011
Name nom
Goldak, John
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
2107
Research subject group en
Mechanical engineering
Research subject group fr
Génie mécanique
Research subject en
Modelling, simulation and finite element methods
Research subject fr
Modélisation, simulation et méthodes des éléments finis
Partie
3
Nb partie
4
Application title
Parametric Structural Design of GEN IV Canadian Super Critical Water Reactor (SCWR)
Keyword
NSERC
Application summary
A parametric solid mechanics model for the design of the reactor core of the GEN IV Canadian Supercritical Water Reactor (SCWR)will be developed to predict transient temperature, displacement, strain and stress fields in the reactor core in the early design stages. The model would be based on 3D transient FEM thermal-stress analysis for normal operation, startup, shut-down, upset and accident conditions. The model would be coupled to the best available estimates of fluid flow velocities, pressures, temperatures and densities. Temperature and if needed microstructure dependent properties would be used. The model would include non-linear contact elements for thermal and stress analysis based on the best available knowledge and if not available, sensitivity studies would be helpful, of the gap width, surface roughness, gap material of each contact interface.
