Analysis of Thorium Performance in Lead cooled Fast Reactor

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

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

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

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

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

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

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

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

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