TY - JOUR
T1 - A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors
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 .
Funding Information:
This work 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:
© 2019 Elsevier Ltd
PY - 2020/5
Y1 - 2020/5
N2 - This work presents the development of a coupling scheme for Serpent2, a continuous-energy Monte Carlo particle transport code, SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance code, suitable for large-scale high-fidelity depletion calculations for Light Water Reactors. The calculation method is based on the standard neutronic-thermalhydraulic approach, replacing the simple fuel-rod solver in SUBCHANFLOW with the more complex thermomechanic model of TRANSURANUS. The depletion method is fully coupled and semi-implicit, and the implementation relies on an object-oriented design with mesh-based feedback exchange. The results of the three-code system for a 360-day depletion calculation of a VVER-1000 fuel assembly with a pin-by-pin modelling approach are presented and analyzed. The performance of this tool, as well as the bottlenecks for its application to full-core problems, are discussed.
AB - This work presents the development of a coupling scheme for Serpent2, a continuous-energy Monte Carlo particle transport code, SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance code, suitable for large-scale high-fidelity depletion calculations for Light Water Reactors. The calculation method is based on the standard neutronic-thermalhydraulic approach, replacing the simple fuel-rod solver in SUBCHANFLOW with the more complex thermomechanic model of TRANSURANUS. The depletion method is fully coupled and semi-implicit, and the implementation relies on an object-oriented design with mesh-based feedback exchange. The results of the three-code system for a 360-day depletion calculation of a VVER-1000 fuel assembly with a pin-by-pin modelling approach are presented and analyzed. The performance of this tool, as well as the bottlenecks for its application to full-core problems, are discussed.
KW - LWR
KW - Multiphysics
KW - Serpent2
KW - SUBCHANFLOW
KW - TRANSURANUS
UR - http://www.scopus.com/inward/record.url?scp=85075562244&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2019.107213
DO - 10.1016/j.anucene.2019.107213
M3 - Article
AN - SCOPUS:85075562244
VL - 139
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
SN - 0306-4549
M1 - 107213
ER -