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

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

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

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

Efficient Evaluation of Heat Exchangers Behaviour in Nuclear Power Plants

Analysis of Fuel Burn-up Calculations of 3600 MWth Sodium cooled Fast Reactor Core

Using Thorium Based Fuel in AP1000: Steady State Analysis

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

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