Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor
•MBurnup scheme with fully coupled Monte Carlo neutronics, subchannel thermalhydraulics and fuel-performance analysis.•Validation for the beginning of the first operating cycle of a Pre-Konvoi PWR plant.•Deviations between results and experimental data bellow 10 ppm for the critical boron concentrat...
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Veröffentlicht in: | Nuclear engineering and design 2021-08, Vol.379, p.111173, Article 111173 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | •MBurnup scheme with fully coupled Monte Carlo neutronics, subchannel thermalhydraulics and fuel-performance analysis.•Validation for the beginning of the first operating cycle of a Pre-Konvoi PWR plant.•Deviations between results and experimental data bellow 10 ppm for the critical boron concentration.•Pin-level neutron flux profiles in very good agreement with aeroball measurements.•Assessment of the impact of including fuel-performance capabilities.
The focus of this work is the validation of Serpent-SUBCHANFLOW-TRANSURANUS, a high-fidelity multiphysics system coupling Monte Carlo neutron transport, subchannel thermalhydraulics and fuel-performance analysis. A full-core pin-by-pin burnup calculation for the first operating cycle of a Pre-Konvoi PWR plant is presented and the results are assessed using experimental data. The critical boron concentration and a set of pin-level neutron flux profiles are compared against measurements, with very good agreement. The impact of using fuel-performance analysis is discussed comparing the results obtained with the three-code coupling with the ones using the traditional neutronic-thermalhydraulic approach. The studies presented here are part of the final stage of the EU Horizon 2020 McSAFE project, closing the development cycle of the Serpent-SUBCHANFLOW-TRANSURANUS system, from implementation to validation. |
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ISSN: | 0029-5493 1872-759X |
DOI: | 10.1016/j.nucengdes.2021.111173 |