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

Determination of Temperature Feedback Coefficients for OPR-1000 Fuel Assembly Using Adjusted Cross Section Libraries

Using Thorium Based Fuel in AP1000: Steady State Analysis

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

Simulation of BEAVRS Benchmark at Hot Zero Power Using MCNP6

Thermal-hydraulic Simulation of a WWR-S Reactor for Reactivity Insertion Accident

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

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

Linearized Mathematical Model for PWR Dynamics Simulation

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