Neutronics and Thermal Hydraulic Coupling Methods for the Nuclear Reactor Core
Khan Salah Ud-Din, Minjun Peng, Muhammad Zubair
Abstract
Khan Salah Ud-Din, Minjun Peng, Muhammad Zubair
Abstract
In this paper an overview of the coupling methodologies between reactor physics (Neutronics) and thermal hydraulic have been studied by taken into account the previous and ongoing research. The current study includes the neutronics and thermal hydraulic model and the coupling methodology between the two phenomenons which is inter related with computational approach. Since the coupling involves some computer codes which exchanges the data between the neutronics and thermal hydraulic so in this paper possible computer codes are also have been listed with their categories. Finally the advantages of the coupling are described with some suggestions and conclusion is also given.
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In this paper an overview of the coupling methodologies between reactor physics (Neutronics) and thermal hydraulic have been studied by taken into account the previous and ongoing research. The current study includes the neutronics and thermal hydraulic model and the coupling methodology between the two phenomenons which is inter related with computational approach. Since the coupling involves some computer codes which exchanges the data between the neutronics and thermal hydraulic so in this paper possible computer codes are also have been listed with their categories. Finally the advantages of the coupling are described with some suggestions and conclusion is also given.
Key concepts: Neutron transport, Thermal hydraulics, Coupling (piping), Nuclear engineering, Computer science, Thermal, Nuclear reactor, Core (optical fiber)