CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development

Sebastian Davies, Ulrich Rohde, Dzianis Litskevich, Bruno Merk, Paul Bryce, Andrew Levers, Anna Detkina, Seddon Atkinson and Venkata Ravindra
Additional contact information
Sebastian Davies: School of Engineering, University of Liverpool, Liverpool L69 3GH, UK
Ulrich Rohde: Institute of Innovation, Helmholtz Zentrum Dresden Rossendorf, 01328 Dresden, Germany
Dzianis Litskevich: School of Engineering, University of Liverpool, Liverpool L69 3GH, UK
Bruno Merk: School of Engineering, University of Liverpool, Liverpool L69 3GH, UK
Paul Bryce: EDF Energy, Gloucester GL4 3RS, UK
Andrew Levers: School of Engineering, University of Liverpool, Liverpool L69 3GH, UK
Anna Detkina: School of Engineering, University of Liverpool, Liverpool L69 3GH, UK
Seddon Atkinson: School of Engineering, University of Liverpool, Liverpool L69 3GH, UK
Venkata Ravindra: School of Engineering, University of Liverpool, Liverpool L69 3GH, UK

Energies, 2021, vol. 14, issue 5, 1-27

Abstract: Simulation codes allow one to reduce the high conservativism in nuclear reactor design improving the reliability and sustainability associated with nuclear power. Full-core coupled reactor physics at the rod level are not provided by most simulation codes. This has led in the UK to the development of a multiscale and multiphysics software development focused on LWRS. In terms of the thermal hydraulics, simulation codes suitable for this multiscale and multiphysics software development include the subchannel code CTF and the thermal hydraulics module FLOCAL of the nodal code DYN3D. In this journal article, CTF and FLOCAL thermal hydraulics validations and verifications within the multiscale and multiphysics software development have been performed to evaluate the accuracy and methodology available to obtain thermal hydraulics at the rod level in both simulation codes. These validations and verifications have proved that CTF is a highly accurate subchannel code for thermal hydraulics. In addition, these verifications have proved that CTF provides a wide range of crossflow and turbulent mixing methods, while FLOCAL in general provides the simplified no-crossflow method as the rest of the methods were only tested during its implementation into DYN3D.

Keywords: nuclear reactor; thermal hydraulics; simulation; subchannel code; CTF; FLOCAL; PSBT (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2021
References: View complete reference list from CitEc
Citations: View citations in EconPapers (3)

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