Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Efficient Evaluation of Heat Exchangers Behaviour in Nuclear Power Plants

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

THERMAL PERFORMANCE OF A TWO-PHASE CLOSED THERMOSYPHON

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

Investigation of Thermal Hydraulic Behavior of Dry Spent Fuel Cask Under Forced Convection

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

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

Thermal-Hydraulic Simulation of Cold Water Spray in a Nuclear Power Plant Containment