Artículos en revistas:
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
Año:2018
Áreas de investigación
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Centrales térmicas nucleares y de fusión
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Descripción
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| At UPM, in-depth modifications of the core simulator COBAYA, able to perform neutronics diffusion calculations at both nodal and pin-by-pin levels, have been accomplished during the 7th Framework EURATOM NURESAFE project. The main goal was to upgrade its integration in the European Platform for Nuclear Reactor Safety Simulation in order to facilitate the coupling with any other code of the platform for multi-physics analysis, focusing also on the code legibility and maintainability. An external and flexible coupling with the thermal-hydraulics code COBRA-TF was designed. As a result, COBAYA4/COBRA-TF allows multiscale coupled calculations, enabling both nodal and pin-by-pin neutronics resolutions using both assembly-based channels and pin-based subchannels at the thermal-hydraulics domain. Flexible mapping schemes also in axial direction can be defined. The coupled system was applied to a Main Steam Line Break transient benchmark. Pin-by-pin 3D simulations using one thermal-hydraulic channel per assembly were carried out in a reasonable computing time, and results compared to nodal solutions demonstrating the multiscale coupling capability for full core transients. Pin-by-pin calculations using thermal-hydraulics subchannels will be performed in a near future to assess the role that a very detailed mapping can play to predict realistic local parameters. While in asymmetric transients the effect can be important, it is expected that in symmetric transients assembly-based thermal-hydraulics channels can provide accurate pin-by-pin solutions in execution times suitable for routine analysis. The performed work will bring the ability to explore in an easy way multiscale effects on safety transient evaluations and give recommendations for the neutronics/thermal-hydraulics mapping depending on the application. | |
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Internacional
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JCR del ISI
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Título de la revista
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Nuclear Engineering and Design |
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ISSN
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0029-5493 |
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Factor de impacto JCR
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0,967 |
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Información de impacto
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Volumen
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321 |
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DOI
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Número de revista
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Desde la página
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38 |
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Hasta la página
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47 |
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Mes
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SEPTIEMBRE |
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Ranking
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Participantes
- Autor: Nuria Garcia Herranz (UPM)
- Autor: Diana Cuervo Gomez (UPM)
- Autor: Adrian Sabater Alcaraz (UPM)
- Autor: Gabriel Rucabado Rucabado (UPM)
- Autor: Santiago Sanchez-Cervera Huerta (UPM)
- Autor: Emilio Castro Gonzalez (UPM)
Grupos de investigación, Departamentos, Centros e Institutos de I+D+i relacionados
- Creador: Centro o Instituto I+D+i: Instituto de Fusión Nuclear "Guillermo Velarde"
- Departamento: Ingeniería Energética
S2i 2023 Observatorio de investigación @ UPM con la colaboración del Consejo Social UPM
Cofinanciación del MINECO en el marco del Programa INNPACTO (IPT-020000-2010-22)