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

Manuel García; Radim Vo cka; Riku Tuominen; Andre Gommlich; Jaakko Leppanen; Ville Valtavirta; Uwe Imke; Diego Ferraro; Paul Van Uffelen; Luka s Milisdorfer; Victor Sanchez-Espinoza

doi:https://doi.org/10.1016/j.net.2021.04.023

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저자정보: Manuel García (Karlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von) Radim Vo cka (ÚJV Re z a. s) Riku Tuominen (VTT Technical Research Centre of Finland Ltd.,) Andre Gommlich (Helmholtz-Zentrum Dresden-Rossendorf, Institute of Resource Ecology, Bautzner Landstraße) Jaakko Leppanen (VTT Technical Research Centre of Finland Ltd.,) Ville Valtavirta (VTT Technical Research Centre of Finland Ltd.,) Uwe Imke (Karlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von) Diego Ferraro (Karlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von) Paul Van Uffelen (Joint Research Centre, European Commission, Hermann-von-Helmholtz-Platz 1, 76344, Eggenstein-Leopol) Luka s Milisdorfer (CEZ a. s, Duhova 2 / 1444, Prague, Czech Republi) Victor Sanchez-Espinoza (Karlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제10호

발행연도: 2021.10

수록면: 3,133 - 3,150 (18page)

DOI: https://doi.org/10.1016/j.net.2021.04.023

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This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 MonteCarlo 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 forthe ninth operating cycle of the Temelin II VVER-1000 plant, which starts from a fresh core, are presentedand 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 calculatedaxial and radial power distributions match closely the values reported by the core monitoring system. Todemonstrate the modeling capabilities of the three-code coupling, pin-level neutronic, thermalhydraulicand thermomechanic results are shown as well. These studies are encompassed in the final phase of theEU Horizon 2020 McSAFE project, during which the Serpent-SUBCHANFLOW-TRANSURANUS system wasdeveloped

#Monte Carlo neutron #transport #Subchannel thermalhydraulics #Fuel-performance analysis #High-fidelity multiphysics #Pin-level burnup #VVER-1000

참고문헌 (24)

참고문헌 신청

V. Sanchez-Espinoza / 2020 / The McSAFE project -high-performance Monte Carlo based methods for safety demonstration: from proof of concept to industry applications / PHYSOR 2020 Conference

Jaakko Leppänen / 2015 / The Serpent Monte Carlo code: Status, development and applications in 2013 / Annals of Nuclear Energy 82:142~150

U. Imke / 2012 / Validation of the subchannel code SUBCHANFLOW using the NUPEC PWR tests (PSBT) / Science and Technology of Nuclear Installations 0

P. Van Uffelen / 2008 / Extending the application range of a fuel performance code from normal operating to design basis accident conditions / Journal of Nuclear Materials 383(1-2):137~143

Manuel García / 2020 / A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors / Annals of Nuclear Energy 139:107213

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Manuel García

소속기관 Karlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Hermann-von