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

Neutronic Analysis of Heavy Water Application in HPLWR Emergency Core Cooling System

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

Evaluation of a Primary Treatment Unit for the Cooling Water of a Nuclear Power Plant

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Modeling of Passive Safety Thermosyphon Loops Cooling System for Nuclear Applications

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

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

Efficient Evaluation of Heat Exchangers Behaviour in Nuclear Power Plants

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