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

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

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

Steady State Thermal Hydraulic Model for PWR Light Water Reactors

Experimental Investigation of Heat Transfer from a Vertical Rod-Bundle into Two-Phase Flow.

Linearized Mathematical Model for PWR Dynamics Simulation

Critical Heat Flux in Convective Boiling in Nuclear Reactors.

Investigation of Pressure Drop on Upward Two-Phase Flow in a Vertical Rod-Bundle.

Comparative Study of Kinetic Hydrodynamic Theoretical Model Results in Fluidized Bed Reactor Using Different Fuels.

Thermal Hydraulic Evaluation of a proposed annular Fuel for VVER1000 Reactor