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

García, Manuel; Vočka, Radim; Tuominen, Riku; Gommlich, Andre; Leppänen, Jaakko; Valtavirta, Ville; Imke, Uwe; Ferraro, Diego; Van Uffelen, Paul; Milisdörfer, Lukáš; Sanchez-Espinoza, Victor

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.

Verlagsausgabe §
DOI: 10.5445/IR/1000133665
Veröffentlicht am 08.06.2021
DOI: 10.1016/
Zitationen: 1
Zitationen: 2
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2021
Sprache Englisch
Identifikator ISSN: 1738-5733, 0372-7327, 2234-358X
KITopen-ID: 1000133665
HGF-Programm 32.12.01 (POF IV, LK 01) Design Basis Accidents and Materials Research
Erschienen in Nuclear Engineering and Technology
Verlag Elsevier
Schlagwörter Monte Carlo neutron transport; Subchannel thermalhydraulics; Fuel-performance analysis; High-fidelity multiphysics; Pin-level burnup; VVER-1000
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