MEng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2017In 1996 the U.S Nuclear Regulatory Commission issued a notice that addressed the operation of pressurised water reactors (PWR’s) above the licensed power limit due to a decrease in the feed water temperature which may also affect the measuring accuracy of nuclear instrumentation. The designed feed water operating temperature range may be inaccurate due to various assumptions made, including that of an equilibrium steady state approach which represents the conditions of the open feed water heater (OFWH). The aim of the study is to simulate the open feed water heater for application in a high-performance light water reactor (HPLWR), using a non-equilibrium two-...
Boiling flow systems such as boiling water nuclear reactors and once-through steam generators may be...
Counter-Current Flow Limitation (CCFL) is of importance for PWR safety analyses in several accident ...
This thesis describes the development and verification of a nonequilibrium drift-flux steam generato...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014The modelling of multi-...
Thermal hydraulics in nuclear engineering including multifluid, multiphase flow phenomena is indispe...
This thesis describes the mathematical modelling and analysis of the two phase flow of water and ste...
An existing computer model for emergency core cooling reflood heat transfer has been modified to des...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
This work has theoretically studied the steady state and transient characteristics of an electricall...
The safe operation of a two-phase heat exchanger can be performed by determining the instability thr...
Graduation date: 1984A vital safety concern in the analysis of nuclear power reactors\ud is the ther...
This paper deals with a new Control Oriented Model (COM) aimed at studying the dynamic behaviour of ...
This report analyzes severe water ingress accidents in the SIEMENS 200MW Modular Pebble-Bed High Tem...
The boiling process is utterly fundamental to the design and safety of water-cooled fission reactors...
Boiling heat transfer system keeps a nuclear power plant safe without getting over-heated. Crisis wi...
Boiling flow systems such as boiling water nuclear reactors and once-through steam generators may be...
Counter-Current Flow Limitation (CCFL) is of importance for PWR safety analyses in several accident ...
This thesis describes the development and verification of a nonequilibrium drift-flux steam generato...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014The modelling of multi-...
Thermal hydraulics in nuclear engineering including multifluid, multiphase flow phenomena is indispe...
This thesis describes the mathematical modelling and analysis of the two phase flow of water and ste...
An existing computer model for emergency core cooling reflood heat transfer has been modified to des...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
This work has theoretically studied the steady state and transient characteristics of an electricall...
The safe operation of a two-phase heat exchanger can be performed by determining the instability thr...
Graduation date: 1984A vital safety concern in the analysis of nuclear power reactors\ud is the ther...
This paper deals with a new Control Oriented Model (COM) aimed at studying the dynamic behaviour of ...
This report analyzes severe water ingress accidents in the SIEMENS 200MW Modular Pebble-Bed High Tem...
The boiling process is utterly fundamental to the design and safety of water-cooled fission reactors...
Boiling heat transfer system keeps a nuclear power plant safe without getting over-heated. Crisis wi...
Boiling flow systems such as boiling water nuclear reactors and once-through steam generators may be...
Counter-Current Flow Limitation (CCFL) is of importance for PWR safety analyses in several accident ...
This thesis describes the development and verification of a nonequilibrium drift-flux steam generato...