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

Thermal-hydraulic Simulation of a WWR-S Reactor for Reactivity Insertion Accident

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM

Neutronics and Thermal Hydraulic Coupling Analysis for MTR Reactors

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

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Linearized Mathematical Model for PWR Dynamics Simulation

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

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

Calculation of dose rates in loss of coolant accident due to double ended rupture of the experimental tangential irradiation beam tube of MTR reactor.