Large-eddy simulation, fuel rod vibration and grid-to-rod fretting in pressurized water reactors
Grid-to-rod fretting (GTRF) in pressurized water reactors is a flow-induced vibration
phenomenon that results in wear and fretting of the cladding material on fuel rods. GTRF is …
phenomenon that results in wear and fretting of the cladding material on fuel rods. GTRF is …
Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors
The grid-to-rod fretting (GTRF) problem in pressurized water reactors is a flow-induced
vibration problem that results in wear and failure of the fuel rods in nuclear assemblies. In …
vibration problem that results in wear and failure of the fuel rods in nuclear assemblies. In …
Assessment of advanced boiling flow and heat transfer models for PHWR conditions
K Podila, Y Rao, G Waddington, C Li - Progress in Nuclear Energy, 2022 - Elsevier
This paper presents an assessment of advanced two-phase flow and wall boiling models for
prediction of critical heat flux (CHF) of the annular-flow liquid-film dryout type, which is …
prediction of critical heat flux (CHF) of the annular-flow liquid-film dryout type, which is …
[PDF][PDF] GTRF Calculations Using Hydra-TH (L3 Milestone THM. CFD. P5. 05)
This report describes the work carried out for completion of the Thermal Hydraulics Methods
(THM) Level 3 Milestone THM. CFD. P5. 05 for the Consortium for Advanced Simulation of …
(THM) Level 3 Milestone THM. CFD. P5. 05 for the Consortium for Advanced Simulation of …
A comparative study of the commercial CFD codes: ANSYS Fluent and STAR-CCM+ to simulate nuclear fuel bundles
K Podila, YF Rao - 2015 - inis.iaea.org
This paper presents an overview of the capability of two commercial computational fluid
dynamics (CFD) codes, ANSYS Fluent and STAR-CCM+, for simulating flow and heat …
dynamics (CFD) codes, ANSYS Fluent and STAR-CCM+, for simulating flow and heat …
[PDF][PDF] Hydra-TH: A Thermal-Hydraulics Code for Nuclear Reactor Applications RR Nourgaliev Nuclear Science & Technology, NST Idaho National Laboratory PO Box …
Hydra-TH is a hybrid finite-volume/finite-element multi-physics code that is being developed
for the Consortium for Advanced Simulation of Light-Water Reactors to solve thermal …
for the Consortium for Advanced Simulation of Light-Water Reactors to solve thermal …
[PDF][PDF] IAEA Nuclear Energy Series
ESN NF-T - www-pub.iaea.org
1.1. BACKGROUND The results of a fuel failure analysis were published in the IAEA's
journal Atomic Energy Review in 1979 under the title The Main Causes of Fuel Element …
journal Atomic Energy Review in 1979 under the title The Main Causes of Fuel Element …