Analysis of Thorium Performance in Lead cooled Fast Reactor

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Using Thorium Based Fuel in AP1000: Steady State Analysis

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

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

"PREDICTION THE PERFORMANCE OF THE IAEA 10 MW MTR RESEARCH REACTOR AT TRANSIENT STARTUP"

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

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

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

A THERMAL HYDRAULIC MODEL FOR POWER UPGRADING OF WWR-S RESEARCH REACTOR