Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

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

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

Analysis of Thorium Performance in Lead cooled Fast Reactor

Using Thorium Based Fuel in AP1000: Steady State Analysis

Linearized Mathematical Model for PWR Dynamics Simulation

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

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