Thermal hydraulic analysis of nuclear reactor core is mainly performed using the sub-
channel analysis codes to estimate different thermal hydraulic safety margins. The safety …

In commercial computational fluid dynamics codes there is more than one turbulence model
built in. It is the user responsibility to choose one of those models, suitable for the problem …

Flow behavior inside the sub-channel is of paramount importance for the operation and
safety of the nuclear reactor. CFD simulations are becoming popular for these computations …

The hydraulic characteristics in subchannels of axially finned rod bundles installed in the
Korea Multipurpose Research Reactor (KMRR) were measured using one-component laser …

This paper presents in detail the hydraulic characteristic measurements using LDV (Laser
Doppler Velocimetry) in subchannels of a HANARO, KAERI research reactor, fuel bundle …

[en] The objective of this project is to obtain the experimental data of pressure drop and
microscopic turbulent flow structure in subchannels for the KMRR fuel assembly, and to …

Detailed measurement of axial pressure profiles is often required to optimize the design of
nuclear fuel assemblies. The classic method of using drilled pressure taps at predetermined …

[en] Single-and two-phase flow experiments have been performed on two strings of 4-rod
bundles: one simulating a string of regular 37-element bundles currently used in CANDU …

Thermal hydraulic investigations in annular channel and rod bundle geometries are basic to
derive research information in designing the coolant subchannels of a nuclear reactor. The …

[en] The Indian Nuclear Power Programme envisages three important stages viz.,
installation of thermal reactors, fast reactors and utilization of Thorium. By the year 2000 AD …