Uncertainties of the KIKO3D-ATHLET calculations using the Kalinin-3 benchmark (Phase II) data
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I. Panka
Abstract
The best estimate simulation of three-dimensional phenomena in nuclear reactor cores requires the use of coupled neutron physics and thermal-hydraulics calculations. However these analyses should be supplemented by the survey of the corresponding uncertainties. In this paper the uncertainties of the coupled KIKO3D-ATHLET calculations are presented for a VVER-1000 type core using the OECD NEA Kalinin-3 (Phase II) benchmark data, although only the neutronic uncertainties are considered and further simplifications are applied and discussed. Additionally, this study has been performed in the conjunction with the OECD NEA UAM benchmark, as well. In the first part of the paper, the uncertainties of the effective multiplication factor, the assembly-wise radial power distribution, the axial power distribution, the rod worth, etc. are presented at steady-state. After that some uncertainties of the transient calculations are discussed for the considered switch-off of one Main Circulation Pump (MCP) type transient.
Kurzfassung
Best-estimate Rechnungen dreidimensionaler Phänomen im Reaktorkern erfordern die Nutzung gekoppelter neutronenphysikalischer und thermohydraulischer Programme und müssen durch Unsicherheitsbetrachtungen ergänzt werden. Dies wird in diesem Beitrag beispielhaft für eine gekoppelte KIKO3D-ATHLET-Rechnungen eines typischen WWER-1000-Reaktorkerns am Beispiel von OECD-NEA-Kalinin-3 (Phase II)-Benchmarkdaten präsentiert. Dabei richtet sich das Hauptaugenmerk auf die neutronenphysikalischen Unsicherheiten unter Berücksichtigung weiterer vereinfachender Annahmen. Diese Untersuchungen wurden im Zusammenhang mit dem OECD-NEA-UAM-Benchmark durchgeführt. Im ersten Teil des Beitrags werden die Unsicherheiten der effektiven Multiplikationsfaktoren, der radialen Leistungsverteilung einzelner Brennelement, der axialen Leistungsverteilung, des Abbrands etc. im stationären Fall vorgestellt. Anschließend folgt die Berechnung einiger Unsicherheiten für die transienten Rechnungen, bei denen der Ausfall einer Hauptkühlmittelpumpe unterstellt wurde.
References
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© 2016, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2015
- Technical Contributions/Fachbeiträge
- Monte-Carlo code calculation of 3D reactor core model with usage of burnt fuel isotopic compositions, obtained by engineering codes
- Xenon instability study of large core Monte Carlo calculations
- Error detection in core loading in the condition of asymmetrical distribution of power
- New models in VERONA 7.0 system
- Methodology for determining of the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations
- Aspects of using a best-estimate approach for VVER safety analysis in reactivity initiated accidents
- Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark – re-connection of an isolated loop
- Uncertainties of the KIKO3D-ATHLET calculations using the Kalinin-3 benchmark (Phase II) data
- Coupled code analysis of uncertainty and sensitivity of Kalinin-3 benchmark
- Efficient introduction of natural uranium and thorium into nuclear energy system
- Economical aspects of multiple plutonium and uranium recycling in VVER reactors
- Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO
- Uncertainty analysis and flow measurements in an experimental mock-up of a molten salt reactor concept
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2015
- Technical Contributions/Fachbeiträge
- Monte-Carlo code calculation of 3D reactor core model with usage of burnt fuel isotopic compositions, obtained by engineering codes
- Xenon instability study of large core Monte Carlo calculations
- Error detection in core loading in the condition of asymmetrical distribution of power
- New models in VERONA 7.0 system
- Methodology for determining of the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations
- Aspects of using a best-estimate approach for VVER safety analysis in reactivity initiated accidents
- Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark – re-connection of an isolated loop
- Uncertainties of the KIKO3D-ATHLET calculations using the Kalinin-3 benchmark (Phase II) data
- Coupled code analysis of uncertainty and sensitivity of Kalinin-3 benchmark
- Efficient introduction of natural uranium and thorium into nuclear energy system
- Economical aspects of multiple plutonium and uranium recycling in VVER reactors
- Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO
- Uncertainty analysis and flow measurements in an experimental mock-up of a molten salt reactor concept
