Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor

This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results for a full-core pin-by-pin burnup calculation for...

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Main Authors: Manuel García, Radim Vočka, Riku Tuominen, Andre Gommlich, Jaakko Leppänen, Ville Valtavirta, Uwe Imke, Diego Ferraro, Paul Van Uffelen, Lukáš Milisdörfer, Victor Sanchez-Espinoza
Format: Article
Language:English
Published: Elsevier 2021-10-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573321002424
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spelling doaj-a33301b22f5342ef95b0f04cb031d0912021-08-06T04:21:12ZengElsevierNuclear Engineering and Technology1738-57332021-10-01531031333150Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactorManuel García0Radim Vočka1Riku Tuominen2Andre Gommlich3Jaakko Leppänen4Ville Valtavirta5Uwe Imke6Diego Ferraro7Paul Van Uffelen8Lukáš Milisdörfer9Victor Sanchez-Espinoza10Karlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1, 76344, Eggenstein-Leopoldshafen, Germany; Corresponding author.ÚJV Řež a. s, Hlavní 130, Řež, Czech RepublicVTT Technical Research Centre of Finland Ltd., P.O. Box 1000, FI-02044, VTT, FinlandHelmholtz-Zentrum Dresden-Rossendorf, Institute of Resource Ecology, Bautzner Landstraße 400, 01328, Dresden, GermanyVTT Technical Research Centre of Finland Ltd., P.O. Box 1000, FI-02044, VTT, FinlandVTT Technical Research Centre of Finland Ltd., P.O. Box 1000, FI-02044, VTT, FinlandKarlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1, 76344, Eggenstein-Leopoldshafen, GermanyKarlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1, 76344, Eggenstein-Leopoldshafen, GermanyJoint Research Centre, European Commission, Hermann-von-Helmholtz-Platz 1, 76344, Eggenstein-Leopoldshafen, GermanyČEZ a. s, Duhová 2 / 1444, Prague, Czech RepublicKarlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1, 76344, Eggenstein-Leopoldshafen, GermanyThis work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results for a full-core pin-by-pin burnup calculation for the ninth operating cycle of the Temelín II VVER-1000 plant, which starts from a fresh core, are presented and assessed using experimental data. A good agreement is found comparing the critical boron concentration and a set of pin-level neutron flux profiles against measurements. In addition, the calculated axial and radial power distributions match closely the values reported by the core monitoring system. To demonstrate the modeling capabilities of the three-code coupling, pin-level neutronic, thermalhydraulic and thermomechanic results are shown as well. These studies are encompassed in the final phase of the EU Horizon 2020 McSAFE project, during which the Serpent-SUBCHANFLOW-TRANSURANUS system was developed.http://www.sciencedirect.com/science/article/pii/S1738573321002424Monte Carlo neutron transportSubchannel thermalhydraulicsFuel-performance analysisHigh-fidelity multiphysicsPin-level burnupVVER-1000
collection DOAJ
language English
format Article
sources DOAJ
author Manuel García
Radim Vočka
Riku Tuominen
Andre Gommlich
Jaakko Leppänen
Ville Valtavirta
Uwe Imke
Diego Ferraro
Paul Van Uffelen
Lukáš Milisdörfer
Victor Sanchez-Espinoza
spellingShingle Manuel García
Radim Vočka
Riku Tuominen
Andre Gommlich
Jaakko Leppänen
Ville Valtavirta
Uwe Imke
Diego Ferraro
Paul Van Uffelen
Lukáš Milisdörfer
Victor Sanchez-Espinoza
Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
Nuclear Engineering and Technology
Monte Carlo neutron transport
Subchannel thermalhydraulics
Fuel-performance analysis
High-fidelity multiphysics
Pin-level burnup
VVER-1000
author_facet Manuel García
Radim Vočka
Riku Tuominen
Andre Gommlich
Jaakko Leppänen
Ville Valtavirta
Uwe Imke
Diego Ferraro
Paul Van Uffelen
Lukáš Milisdörfer
Victor Sanchez-Espinoza
author_sort Manuel García
title Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
title_short Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
title_full Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
title_fullStr Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
title_full_unstemmed Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
title_sort validation of serpent-subchanflow-transuranus pin-by-pin burnup calculations using experimental data from the temelín ii vver-1000 reactor
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2021-10-01
description This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results for a full-core pin-by-pin burnup calculation for the ninth operating cycle of the Temelín II VVER-1000 plant, which starts from a fresh core, are presented and assessed using experimental data. A good agreement is found comparing the critical boron concentration and a set of pin-level neutron flux profiles against measurements. In addition, the calculated axial and radial power distributions match closely the values reported by the core monitoring system. To demonstrate the modeling capabilities of the three-code coupling, pin-level neutronic, thermalhydraulic and thermomechanic results are shown as well. These studies are encompassed in the final phase of the EU Horizon 2020 McSAFE project, during which the Serpent-SUBCHANFLOW-TRANSURANUS system was developed.
topic Monte Carlo neutron transport
Subchannel thermalhydraulics
Fuel-performance analysis
High-fidelity multiphysics
Pin-level burnup
VVER-1000
url http://www.sciencedirect.com/science/article/pii/S1738573321002424
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