Research Papers/Topics in Nuclear Engineering

Investigating The Thermal Hydraulic Performance Of Combined Split And Swirl Vanes Using Star-Ccm+

ABSTRACT For effective evacuation of heat from nuclear fuels and increasing the Critical Heat Flux (CHF) of nuclear fuel bundles, mixing vanes are attached to spacer grids in fuel assemblies. However, the presence of spacer grids increases the pressure drop across the fuel bundle which has economic implications on the operations of Nuclear Power Plants (NPPs) in general. Nuclear fuel vendors are therefore continually improving upon the designs of mixing vanes in order to improve the thermal ...

Stability and Control of Supercritical Water Reactor System: A Study into Concepts and Applications

ABSTRACT The study addresses the stability and control of nuclear systems with emphasis on the Supercritical Water Reactor (SCWR) as proposed in the Generation IV International Forum. The literature on the stability and control of the SCWR is presented. A Computational Fluid Dynamics code, STAR-CCM+, is used to study the flow stability problems in circular channels, fuel bundle slices with and without heating structures. Some of the effects of numerical discretisation, turbulence model effect...

Reactor Core Conversion Studies Of Ghana Research Reactor – 1 And Proposal For Addition Of Safety Rod

ABSTRACT The inclusion of an additional safety rod in conjunction with a core conversion study of Ghana Research Reactor-1 (GHARR-1) was carried out using neutronics, thermal hydraulics and burnup codes. The study is based on a recommendation by Integrated Safety Assessment for Research Reactors (INSARR) mission to incorporate a safety rod to the reactor safety system as well as the need to replace the reactor fuel with LEU. Conversion from one fuel type to another requires a complete re-eval...

Neutronics And Dose Calculation For Prospective Spent Nuclear Fuel Cask For Ghana Research Reactor-1 Facility.

ABSTRACT Ghana Research Reactor-1 core is to be converted from Highly Enrich Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel in the near future; a storage cask will be needed to store the HEU fuel. Notwithstanding the core conversion process, it is also important for the facility to have a storage cask ready when the fuel is finally spent to temporarily store the fuel until permanent storage is provided. Winfrith Improved Multigroup Scheme-Argonne National Laboratory (WIMS-ANL), REactor...