Neutronics and Thermal Hydraulic Coupling Analysis for MTR Reactors

Improving Neutronic Performance of Floating Nuclear Reactor Using Different Fuel Cycles Alternatives

METALIZED FUEL HYBRID ROCKET MOTOR PARAMETRIC STUDY

Investigation of Thermal-Hydraulic Behavior of Supercritical Water Reactor Using Thorium-Uranium Oxide Fuel (ThO2 – UO2)

Using Thorium Based Fuel in AP1000: Steady State Analysis

Analysis of Small Modular SMART Reactor Core Fuel Burn up using MCNPX code

Analysis of Thorium Performance in Lead cooled Fast Reactor

Analysis of Fuel Burn-up Calculations of 3600 MWth Sodium cooled Fast Reactor Core

Results of the Hydraulic Testing of the New Low Enriched Core of Tajoura Research Reactor

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor