Grant: NSERC/NRCan/AECL Generation IV Energy Technologies Program
École Polytechnique de Montréal
$3,995.00
Optimization of the Safety Characteristics of the Generation IV Super Critical Water Reator
FY 2011-12
Summary
Here we propose to analyze the nuclear safety performance of the SCWR, a Generation IV nuclear system, based on the following two considerations: excellence in safety and reliability and a very low likelihood and degree of reactor core damage. Because the SCWR is a nuclear system, its general behavior is controlled by reactor physics, which is used to predict the population of neutrons in the core with time as well as the changes in reactivity resulting from variation in the core properties. These changes may take place as the reactor operates and their impact on the reactor safety must be assessed. One must also minimize the likelihood of core damage that could result from postulated accident scenarios. This implies selecting a fuel configuration that will make the coolant void and power reactivity coefficients negative while optimizing fuel consumption. Finally, the efficiency of the reactivity control mechanism and shutdown systems for operation conditions or during accident scenarios must also be assessed since they play an important role to ensure the safety of the reactor.
Our research program is aimed at characterizing the safety parameters of the SCWR using the chain of reactor physics codes DRAGON (an industry standard toolset (IST) code of the Canadian nuclear industry for lattice cell calculation) and DONJON (a finite reactor diffusion code). It will consist of three parts. We will first generalize the CANDU simulation procedures to the SCWR problem and compute the various safety related parameters associated with the SCWR. Then we will refine these reference models in such a way that environment dependent DRAGON simulations are taken into account in DONJON. Finally we will optimize the SCWR design towards higher safety and improved fuel consumption starting with the fuel and reactivity control devices. We will also perform a series of optimization studies from which we will propose a refueling procedure (maximize fuel burnup) as well as locations for the reactivity control mechanisms and neutron detector (optimized for effectiveness) in the core.
Program
NSERC/NRCan/AECL Generation IV Energy Technologies Program
Recipient
Location
Quebec, Canada
Recipient Type
Academia
Type
Grant
Source
NSERC's Awards Data
As published
Application id
376350-2008
Name nom
Marleau, Guy
Department département
Génie physique
Organization id
64
Institution établissement
École Polytechnique de Montréal
Province en
Québec
Province fr
Québec
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
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
2401
Research subject group en
Nuclear engineering
Research subject group fr
Génie nucléaire
Research subject en
Reactor design and operation
Research subject fr
Conception et fonctionnement des réacteurs
Partie
3
Nb partie
3
Application title
Optimization of the Safety Characteristics of the Generation IV Super Critical Water Reator
Keyword
NSERC
Application summary
Here we propose to analyze the nuclear safety performance of the SCWR, a Generation IV nuclear system, based on the following two considerations: excellence in safety and reliability and a very low likelihood and degree of reactor core damage. Because the SCWR is a nuclear system, its general behavior is controlled by reactor physics, which is used to predict the population of neutrons in the core with time as well as the changes in reactivity resulting from variation in the core properties. These changes may take place as the reactor operates and their impact on the reactor safety must be assessed. One must also minimize the likelihood of core damage that could result from postulated accident scenarios. This implies selecting a fuel configuration that will make the coolant void and power reactivity coefficients negative while optimizing fuel consumption. Finally, the efficiency of the reactivity control mechanism and shutdown systems for operation conditions or during accident scenarios must also be assessed since they play an important role to ensure the safety of the reactor.
Our research program is aimed at characterizing the safety parameters of the SCWR using the chain of reactor physics codes DRAGON (an industry standard toolset (IST) code of the Canadian nuclear industry for lattice cell calculation) and DONJON (a finite reactor diffusion code). It will consist of three parts. We will first generalize the CANDU simulation procedures to the SCWR problem and compute the various safety related parameters associated with the SCWR. Then we will refine these reference models in such a way that environment dependent DRAGON simulations are taken into account in DONJON. Finally we will optimize the SCWR design towards higher safety and improved fuel consumption starting with the fuel and reactivity control devices. We will also perform a series of optimization studies from which we will propose a refueling procedure (maximize fuel burnup) as well as locations for the reactivity control mechanisms and neutron detector (optimized for effectiveness) in the core.