Calculation of Iodine-131 Concentration inNeutral and Stable ConditionsUsing Three - Dimensions Advection-DiffusionEquation

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

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

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

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

Radiological Characterization and Safety during Decommissioning of aNuclear Reactor

Using Thorium Based Fuel in AP1000: Steady State Analysis

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

Determination of Uranium Isotopic Ratios by Alpha Spectrometry for Nuclear Materials Control Purposes