Stresses Induced by LOCA in Steam Generator Collector of VVER1000

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

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

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

Linearized Mathematical Model for PWR Dynamics Simulation

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Calculation of Corrosion Rate in Ex-reactor Considering the Reactor Effects on the (VVER-1000) fuel clad

MODELING OF A TOTAL LOSS OF POOL WATER ACCIDENT IN MTR REACTOR

The Models Used in Predicting Steam Condensation Occurs during Nuclear Reactor Loss of Coolant Accident