Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

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

Linearized Mathematical Model for PWR Dynamics Simulation

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

Comparing the Neutronic Behavior of LR-0 Reactor During the First 20 Shakes ‎from Startup When Controlled by Boron vs. Silver Control Rods

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

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

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Sensitivity and Uncertainty Analysis of BEAVRS Benchmark

An Enhanced Numerical One-Dimensional Transient Fuel Rod Code for Light Water Reactors.