Validation of MOOSE’s subchannel module using the AREVA FCTF heated bundle benchmark-Reference-Cited by-同舟云学术

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Validation of MOOSE’s subchannel module using the AREVA FCTF heated bundle benchmark

Published:2024-11 Issue: Volume:428 Page:113562
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kyriakopoulos Vasileios^ORCID,Retamales Mauricio Tano

Funder

INL

Publisher

Elsevier BV

Reference12 articles.

1. Subchannel thermal analysis of rod bundle cores;Chelemer;Nucl. Eng. Des.,1972

2. The upgraded cheng and todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles;Chen;Nucl. Eng. Des.,2018

3. Critical heat flux and turbulent mixing in hexagonal tight rod bundles;Cheng;Int. J. Multiph. Flow,1998

4. 3.0 - MOOSE: Enabling massively parallel multiphysics simulations;Giudicelli;SoftwareX,2024

5. Demonstration of pronghorn’s subchannel code modeling of liquid-metal reactors and validation in normal operation conditions and blockage scenarios;Kyriakopoulos;Energies,2023

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