This Study is performed to assess the Canadian pre-conceptual SCWR design for Loss of Flow events leading to degraded cooling conditions and to assess the quality of the CATHENA predictions under supercritical pressure conditions and the unique features which occur under these conditions. / Thesis / Master of Applied Science (MASc)

The purpose of this study was to serve as a starting point in gaining understanding and experience of simulating a typical Pool Type Research Reactor with the thermal hydraulic software code Flownex®. During the study the following evaluations of Flownex® were done: * Assessment of the simplifying assumptions and possible shortcomings built into the software. * Definition of the applicable modelling methodology and further simplifying assumptions that have to be made by the user. * Evaluation of the accuracy and compatibility with the Pool Type Research Reactor. * Comparing the results of this study with similar studies found in the open literature. For the study the IAEA MTR 10 MW benchmark reactor (IAEA, 1992a) was used. A steady state simulation using Flownex® was done on a single fuel assembly, and this was compared with a model that was developed using the software package EES (Engineering Equation Solver). The results have shown good agreement between the different packages. After this verification, a steady state simulation of the entire core was done to obtain the characteristics of the reactor operating under normal condition. Finally, transient simulations were done on various LOFAs (Loss of Flow Accidents). The results of the various LOFAs were compared with studies that were previously done on the IAEA MTR 10 MW reactor. / Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2012.

The purpose of this study was to serve as a starting point in gaining understanding and experience of simulating a typical Pool Type Research Reactor with the thermal hydraulic software code Flownex®. During the study the following evaluations of Flownex® were done: * Assessment of the simplifying assumptions and possible shortcomings built into the software. * Definition of the applicable modelling methodology and further simplifying assumptions that have to be made by the user. * Evaluation of the accuracy and compatibility with the Pool Type Research Reactor. * Comparing the results of this study with similar studies found in the open literature. For the study the IAEA MTR 10 MW benchmark reactor (IAEA, 1992a) was used. A steady state simulation using Flownex® was done on a single fuel assembly, and this was compared with a model that was developed using the software package EES (Engineering Equation Solver). The results have shown good agreement between the different packages. After this verification, a steady state simulation of the entire core was done to obtain the characteristics of the reactor operating under normal condition. Finally, transient simulations were done on various LOFAs (Loss of Flow Accidents). The results of the various LOFAs were compared with studies that were previously done on the IAEA MTR 10 MW reactor. / Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2012.