Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis

García Herranz, Nuria and Cuervo Gómez, Diana and Sabater Alcaraz, Adrián and Rucabado Rucabado, Gabriel and Sánchez-Cervera Huerta, Santiago and Castro González, Emilio (2017). Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis. "Nuclear Engineering and Design", v. 321 ; pp. 38-47. ISSN 0029-5493. https://doi.org/10.1016/j.nucengdes.2017.03.017.

Description

Title: Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
Author/s:
  • García Herranz, Nuria
  • Cuervo Gómez, Diana
  • Sabater Alcaraz, Adrián
  • Rucabado Rucabado, Gabriel
  • Sánchez-Cervera Huerta, Santiago
  • Castro González, Emilio
Item Type: Article
Título de Revista/Publicación: Nuclear Engineering and Design
Date: September 2017
Volume: 321
Subjects:
Freetext Keywords: COBAYA/COBRA-TF; Nodal diffusion; Pin-by-pin diffusion; Multi-scale; Multi-physics; Sub-channel thermal-hydraulics; MSLB transient; Mapping
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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.

Funding Projects

TypeCodeAcronymLeaderTitle
FP7323263NURESAFEUnspecifiedNUCLEAR REACTOR SAFETY SIMULATION PLATFORM

More information

Item ID: 49804
DC Identifier: http://oa.upm.es/49804/
OAI Identifier: oai:oa.upm.es:49804
DOI: 10.1016/j.nucengdes.2017.03.017
Official URL: https://www.sciencedirect.com/science/article/pii/S0029549317301310?via%3Dihub
Deposited by: Memoria Investigacion
Deposited on: 23 Apr 2018 13:58
Last Modified: 19 Mar 2019 15:43
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