SERPENT2-SUBCHANFLOW-TRANSURANUS pin-by-pin depletion calculations for a PWR fuel assembly

Manuel García; Riku Tuominen; Andre Gommlich; Diego Ferraro; Ville Valtavirta; Uwe Imke; Paul van Uffelen; Luigi Mercatali; Victor Sanchez-Espinoza; Jaakko Leppänen; Sören Kliem

doi:10.1051/epjconf/202124706016

SERPENT2-SUBCHANFLOW-TRANSURANUS pin-by-pin depletion calculations for a PWR fuel assembly

Manuel García, Riku Tuominen, Andre Gommlich, Diego Ferraro, Ville Valtavirta, Uwe Imke, Paul van Uffelen, Luigi Mercatali, Victor Sanchez-Espinoza, Jaakko Leppänen, Sören Kliem

BA4501 Reactor analysis

Research output: Contribution to journal › Article in a proceedings journal › Scientific › peer-review

3 Citations (Scopus)

Abstract

This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOWTRANSURANUS. This tool is based on a semi-implicit depletion scheme with pin-by-pin feedback, mesh-based field exchange and an object-oriented software design. The impact of including fuel-performance capabilities is analyzed, with focus on high-burnup effects. The treatment of the Doppler feedback to the neutronics is examined as well, in particular the use of radial fuel-temperature profiles or radially averaged values.

Original language	English
Pages (from-to)	1033-1040
Number of pages	8
Journal	EPJ Web of Conferences
Volume	247
DOIs	https://doi.org/10.1051/epjconf/202124706016
Publication status	Published - 2020
MoE publication type	A4 Article in a conference publication
Event	International Conference on Physics of Reactors, PHYSOR 2020: Transition to a Scalable Nuclear Future - Cambridge, United Kingdom Duration: 28 Mar 2020 → 2 Apr 2020

Funding

This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-W?rttemberg and DFG (?Deutsche Forschungsgemeinschaft?). This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-Württemberg and DFG (”Deutsche Forschungsgemeinschaft”).

Keywords

Multiphysics
PWR
Serpent2
SUBCHANFLOW
TRANSURANUS

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10.1051/epjconf/202124706016Licence: CC BY

Cite this

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title = "SERPENT2-SUBCHANFLOW-TRANSURANUS pin-by-pin depletion calculations for a PWR fuel assembly",

abstract = "This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOWTRANSURANUS. This tool is based on a semi-implicit depletion scheme with pin-by-pin feedback, mesh-based field exchange and an object-oriented software design. The impact of including fuel-performance capabilities is analyzed, with focus on high-burnup effects. The treatment of the Doppler feedback to the neutronics is examined as well, in particular the use of radial fuel-temperature profiles or radially averaged values.",

keywords = "Multiphysics, PWR, Serpent2, SUBCHANFLOW, TRANSURANUS",

author = "Manuel Garc{\'i}a and Riku Tuominen and Andre Gommlich and Diego Ferraro and Ville Valtavirta and Uwe Imke and {van Uffelen}, Paul and Luigi Mercatali and Victor Sanchez-Espinoza and Jaakko Lepp{\"a}nen and S{\"o}ren Kliem",

note = "Funding Information: This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-W?rttemberg and DFG (?Deutsche Forschungsgemeinschaft?). Funding Information: This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-W{\"u}rttemberg and DFG (”Deutsche Forschungsgemeinschaft”). Publisher Copyright: {\textcopyright} The Authors, published by EDP Sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0/).; International Conference on Physics of Reactors, PHYSOR 2020 : Transition to a Scalable Nuclear Future ; Conference date: 28-03-2020 Through 02-04-2020",

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AU - García, Manuel

AU - Tuominen, Riku

AU - Gommlich, Andre

AU - Ferraro, Diego

AU - Valtavirta, Ville

AU - Imke, Uwe

AU - van Uffelen, Paul

AU - Mercatali, Luigi

AU - Sanchez-Espinoza, Victor

AU - Leppänen, Jaakko

AU - Kliem, Sören

N1 - Funding Information: This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-W?rttemberg and DFG (?Deutsche Forschungsgemeinschaft?). Funding Information: This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-Württemberg and DFG (”Deutsche Forschungsgemeinschaft”). Publisher Copyright: © The Authors, published by EDP Sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0/).

PY - 2020

Y1 - 2020

N2 - This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOWTRANSURANUS. This tool is based on a semi-implicit depletion scheme with pin-by-pin feedback, mesh-based field exchange and an object-oriented software design. The impact of including fuel-performance capabilities is analyzed, with focus on high-burnup effects. The treatment of the Doppler feedback to the neutronics is examined as well, in particular the use of radial fuel-temperature profiles or radially averaged values.

AB - This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOWTRANSURANUS. This tool is based on a semi-implicit depletion scheme with pin-by-pin feedback, mesh-based field exchange and an object-oriented software design. The impact of including fuel-performance capabilities is analyzed, with focus on high-burnup effects. The treatment of the Doppler feedback to the neutronics is examined as well, in particular the use of radial fuel-temperature profiles or radially averaged values.

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SERPENT2-SUBCHANFLOW-TRANSURANUS pin-by-pin depletion calculations for a PWR fuel assembly

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