Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

Analyze the effect of void fraction on the main operating parameters of the VVER-1200

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

The reactor power effect on the consequences pressure waves after LBLOCA in VVER-1000

Stresses Induced by LOCA in Steam Generator Collector of VVER1000

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

Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

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

Efficient Evaluation of Heat Exchangers Behaviour in Nuclear Power Plants