Grant: NSERC/NRCan/AECL Generation IV Energy Technologies Program
University of Ontario Institute of Technology
$80,000.00
Study of Kinetics Characteristics of a Pressure-Tube Supercritical-Water Reactor
FY 2014-15
Summary
The Pressure-Tube Supercritical-Water-Cooled Reactor (PT-SCWR) is one of the major nuclear-reactor concepts pursued as part of the cooperative international endeavour known as the Generation IV International Forum (GIF), to which Canada is a party. Supercritical-Water-Cooled reactors operate at higher temperatures and pressures than current-generation reactors and, consequently, offer the promise of higher thermal efficiency. In order to analyze the safety attributes of the PT-SCWR and to design its control and safety systems, its kinetics characteristics need to be assessed. This project will study four aspects related to the kinetics of the PT-SCWR: The values of the full-core kinetics parameters (delayed neutron fractions and generation time); the sensitivity of the kinetics parameters to variations in local fuel and coolant properties; the flux modes and modal core parameters necessary for the control and flux mapping systems; and the decay-heat characteristics of the SCWR fuel. The research results will contribute to the design and analysis of the PT-SCWR Generation IV advanced reactor concept, which is part of Canada's Gen IV National Program and its international commitments under GIF. At the same time, the tools developed as part of the project are applicable to other reactor types, and will also be applicable to the safety analysis of CANDU reactors in current use.
Program
NSERC/NRCan/AECL Generation IV Energy Technologies Program
Location
Ontario, Canada
Recipient Type
Academia
Type
Grant
Source
NSERC's Awards Data
As published
Application id
424116-2011
Name nom
Nichita, Eleodor
Department département
Energy Systems & Nuclear Science, Faculty of
Organization id
19222
Institution établissement
University of Ontario Institute of Technology
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
2400
Research subject group en
Nuclear engineering
Research subject group fr
Génie nucléaire
Research subject en
Nuclear engineering
Research subject fr
Génie nucléaire
Partie
4
Nb partie
4
Application title
Study of Kinetics Characteristics of a Pressure-Tube Supercritical-Water Reactor
Keyword
NSERC
Application summary
The Pressure-Tube Supercritical-Water-Cooled Reactor (PT-SCWR) is one of the major nuclear-reactor concepts pursued as part of the cooperative international endeavour known as the Generation IV International Forum (GIF), to which Canada is a party. Supercritical-Water-Cooled reactors operate at higher temperatures and pressures than current-generation reactors and, consequently, offer the promise of higher thermal efficiency. In order to analyze the safety attributes of the PT-SCWR and to design its control and safety systems, its kinetics characteristics need to be assessed. This project will study four aspects related to the kinetics of the PT-SCWR: The values of the full-core kinetics parameters (delayed neutron fractions and generation time); the sensitivity of the kinetics parameters to variations in local fuel and coolant properties; the flux modes and modal core parameters necessary for the control and flux mapping systems; and the decay-heat characteristics of the SCWR fuel. The research results will contribute to the design and analysis of the PT-SCWR Generation IV advanced reactor concept, which is part of Canada's Gen IV National Program and its international commitments under GIF. At the same time, the tools developed as part of the project are applicable to other reactor types, and will also be applicable to the safety analysis of CANDU reactors in current use.
