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Boiling Water Reactor Core Analysis by means of an Improved Porous Media Two-phase Flow Approach

Jauregui Chavez, Veronica 1
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract (englisch):

TWOPORFLOW is a thermal-hydraulics simulation code currently under development at the Institute of Neutron Physics and Reactor Technology (INR) of the Karlsruhe Institute of Technology (KIT). It has the capability to simulate single- and two-phase flow in a structured or unstructured porous medium using a 3-D Cartesian geometry. TWOPORFLOW calculates the transient or steady state solution of the mass, momentum, and energy conservation equations for each fluid phase with a semi-implicit numerical procedure based on the implicit continuous Eulerian (ICE) method.
TWOPORFLOW can simulate simple 1-D geometries like heated pipes, fuel assemblies resolving the sub-channel flow between rods or a whole nuclear core using a coarse mesh. Several closure correlations are implemented to model the heat transfer between solid and coolant, phase change, wall friction as well as liquid-vapor momentum coupling.
These models have been not fully evaluated. Important models such as the turbulent mixing and void dispersion were missing.
Consequently, the goal of this doctoral thesis is to extend and improve the simulating capability of TWOPORFLOW regarding the two-phase flow phenomena in Boiling Water Reactors (BWR) by implementing physical models e.g., turbulent mixing, void dispersion, and critical heat flux.
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Volltext §
DOI: 10.5445/IR/1000145632
Veröffentlicht am 09.05.2022
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Hochschulschrift
Publikationsdatum 09.05.2022
Sprache Englisch
Identifikator KITopen-ID: 1000145632
HGF-Programm 32.12.01 (POF IV, LK 01) Design Basis Accidents and Materials Research
Verlag Karlsruher Institut für Technologie (KIT)
Umfang xvii, 141 S.
Art der Arbeit Dissertation
Fakultät Fakultät für Maschinenbau (MACH)
Institut Institut für Neutronenphysik und Reaktortechnik (INR)
Prüfungsdatum 15.10.2021
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Referent/Betreuer Stieglitz, Robert
KIT – Die Forschungsuniversität in der Helmholtz-Gemeinschaft
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