Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

INVESTIGATION OF THERMAL HYDRAULICS PARAMETERS OF VVER-1000/V-320 DURING LOCA ACCIDENT

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

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

Sub-channel thermal-hydraulic analysis for VVER- 1000 generation III PWR

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

Linearized Mathematical Model for PWR Dynamics Simulation

Discharge Simulation of an MTR Pool Type RR due to a Break in the Reactor Tank

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