Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.

An Enhanced Numerical One-Dimensional Transient Fuel Rod Code for Light Water Reactors.

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

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

Qualitative and Quantitative Evaluation for Auxiliary Feed Water System at Pressurized Water Reactor (PWR).

SHIELDING ASSESSMENT OF THE ET:RR-1 REACTOR UNDER POWER UPGRADING.

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

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

Efficient Evaluation of Heat Exchangers Behaviour in Nuclear Power Plants