Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

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

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

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

Core Physics Analysis of An Assembly of HTTR Reactor using Homogeneous and heterogeneous model.

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

Analysis of Thorium Performance in Lead cooled Fast Reactor

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

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

Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM