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

Criticality Safety Analysis for Cask Design with High Discharged Fuel Burnup Using MCNPX Code

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

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

Using Thorium Based Fuel in AP1000: Steady State Analysis

The MOX Fuel Performance Analysis of ALFRED Core Using MCNPX Transport Code

Estimation of the Reactivity Temperature Coefficients of the AP-1000 Reactor by MCNPX Code

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

Analysis of Thorium Performance in Lead cooled Fast Reactor

Neutronic Analysis of Heavy Water Application in HPLWR Emergency Core Cooling System