A review of sub-channel thermal hydraulic codes for nuclear reactor core and future directions

A Moorthi, AK Sharma, K Velusamy - Nuclear Engineering and Design, 2018 - Elsevier
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 …

From discovery to recognition of periodic large scale vortices in rod bundles as source of natural mixing between subchannels—a review

L Meyer - Nuclear Engineering and Design, 2010 - Elsevier
The mixing of cooling fluid in rod bundles from one subchannel to another through the gaps
between the rods reduces the temperature differences in the coolant as well as along the …

Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

GH Yeoh - Experimental and Computational Multiphase Flow, 2019 - Springer
Thermal hydraulic analysis of nuclear reactor core and its associated systems can be
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …

High-resolution flow structure measurements in a rod bundle

AT Ylönen - 2013 - inis.iaea.org
Flow behaviour inside a rod bundle has been an active research topic since the early days
of the nuclear power industry. Of particular interest in previous studies have been topics …

Thermal–hydraulic performance of a 5× 5 rod bundle with spacer grid in a nuclear reactor

D Chen, Y Xiao, S Xie, D Yuan, X Lang, Z Yang… - Applied thermal …, 2016 - Elsevier
The turbulent flow behavior and heat transfer performance of the rod bundle with spacer grid
have significant effect on the thermal–hydraulic characteristics in Pressurized Water Reactor …

CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core

A Salama, SED El-Morshedy - Annals of nuclear energy, 2012 - Elsevier
Two-dimensional simulations of partial and total channel blockage of the IAEA 10MW
generic reactor is performed under both hot and average channel conditions using the CFD …

On the use of (U) RANS and LES approaches for turbulent incompressible single phase flows in nuclear engineering applications

S Benhamadouche - Nuclear Engineering and Design, 2017 - Elsevier
The present paper gives some ideas and guidelines in order to run high quality (U) RANS or
LES computations. The paper starts with (U) RANS approaches, advocating the use of …

Thermal hydraulic review of light water reactor based on subchannel code CTF

X Zhang, N Gui, H Gong, X Yang, J Tu… - Nuclear Engineering and …, 2023 - Elsevier
Studying thermal hydraulics in reactor cores is essential for ensuring the safe operation of
nuclear power plants and advancing the development of reactors and fuel. In the CASL …

Review of fuel assembly and pool thermal hydraulics for fast reactors

F Roelofs, VR Gopala, S Jayaraju, A Shams… - … Engineering and Design, 2013 - Elsevier
Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear
energy production because of their possible efficient use of uranium and the possibility to …

Metal mesh foil bearing: Effect of motion amplitude, rotor speed, static load, and excitation frequency on force coefficients

L San Andrés, TA Chirathadam - 2011 - asmedigitalcollection.asme.org
Metal mesh foil bearings (MMFBs), simple to construct and inexpensive, are a promising
bearing technology for oil-free microturbomachinery operating at high speed and high …