Investigation of the IAEA benchmark problem using MCNP code

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

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

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

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

Sensitivity and Uncertainty Analysis of BEAVRS Benchmark

Linearized Mathematical Model for PWR Dynamics Simulation

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

Using Thorium Based Fuel in AP1000: Steady State Analysis

Steady State Thermal Hydraulic Model for PWR Light Water Reactors