In the present paper a comparative analysis of the thermalhydraulic performance of helical coil and bayonet tube steam generators (SG) is presented. The tool chosen for the analysis is RELAP5-3D/4.0.3. The reference conditions are the ones of the primary and secondary fluids of the SMART Small Modular Reactor. The analysis has been carried out by considering different operating conditions. First, the performance of the SGs in nominal conditions has been compared; subsequently, assuming a power load control at constant average primary temperature, the thermal hydraulic response of the components at different operating conditions has been studied and the helical coil SG results to be the most compact configuration. It’s behavior is characteri...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2016With a shortage of elec...
The present thesis addresses several topics of thermal-hydraulics applied to the heat transfer in th...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant (N...
The paper analyzes the performance of ALFRED steam generator from the thermal-hydraulic point of vie...
Due to the special structure, helical coil once-through steam generators (HCOTSGs) can withstand gre...
A model has been developed in Matlab environment for the thermal hydraulic analysis of helical coil ...
Abstract(#br)The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a critical component...
The helical steam generator is connected to an HTGR-type nuclear reactor called PeLUIt-40 for steam ...
The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for comp...
Helical tube heat exchangers provide better heat transfer characteristics, an improved capability to...
Bayonet tube heat exchangers are a proposed solution for advanced nuclear reactor steam generators a...
This paper deals with the presentation of the developments of an in-house code created for the stead...
This paper deals with the presentation of the developments of an in-house code created for the stead...
A computational model is developed to describe the thermo-fluid-dynamic behaviour of a helically coi...
In the nuclear field, helically coiled tube steam generators (SGs) are considered as a primary optio...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2016With a shortage of elec...
The present thesis addresses several topics of thermal-hydraulics applied to the heat transfer in th...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant (N...
The paper analyzes the performance of ALFRED steam generator from the thermal-hydraulic point of vie...
Due to the special structure, helical coil once-through steam generators (HCOTSGs) can withstand gre...
A model has been developed in Matlab environment for the thermal hydraulic analysis of helical coil ...
Abstract(#br)The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a critical component...
The helical steam generator is connected to an HTGR-type nuclear reactor called PeLUIt-40 for steam ...
The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for comp...
Helical tube heat exchangers provide better heat transfer characteristics, an improved capability to...
Bayonet tube heat exchangers are a proposed solution for advanced nuclear reactor steam generators a...
This paper deals with the presentation of the developments of an in-house code created for the stead...
This paper deals with the presentation of the developments of an in-house code created for the stead...
A computational model is developed to describe the thermo-fluid-dynamic behaviour of a helically coi...
In the nuclear field, helically coiled tube steam generators (SGs) are considered as a primary optio...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2016With a shortage of elec...
The present thesis addresses several topics of thermal-hydraulics applied to the heat transfer in th...
Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant (N...