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

Core calculations of the Molten Salt Fast Reactor using different computational codes

Analysis of Thorium Performance in Lead cooled Fast Reactor

Using Thorium Based Fuel in AP1000: Steady State Analysis

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

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

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

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

Core Physics Analysis of An Assembly of HTTR Reactor using Homogeneous and heterogeneous model.

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM