Thermal-hydraulic insights during a main steam line break in a generic PWR KONVOI reactor with ATHLET 3.1A
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E. Diaz Pescador
Abstract
The present paper gathers the main insights obtained during the numerical simulation of a 10 % main steam line break (MSLB) in a generic German PWR KONVOI reactor with the thermal-hydraulic system code ATHLET 3.1A. The contents of this paper are focused first on the transient thermal-hydraulic calculation during affected steam generator (SG) 1 boil-off and subsequently on the multidimensional fluid mixing study of the overcooled water stream and the coolant in the reactor pressure vessel. With this aim, the boundary conditions from the test PKL G3.1, carried out at the PKL test facility in the framework of the OECD/PKL-II project, are implemented in the simulation over the plant nominal parameters from the KONVOI reactor. The thermal-hydraulic and fluid mixing results obtained in the simulations are qualitatively assessed against suitable experimental data from the PKL and ROCOM test facilities, showing a good agreement between simulation and test behaviour.
Kurzfassung
Im Beitrag werden die wesentlichen Ergebnisse einer numerischen Simulation eines 10 %igen Hauptdampfleitungsbruchs (MSLB) in einem generischen deutschen PWR KONVOI-Reaktor mit dem thermohydraulischen Systemcode ATHLET 3.1A zusammengefasst. Dieser Beitrag befasst sich zunächst mit der transienten thermohydraulischen Berechnung während des Abdampfens des betroffenen Dampferzeugers (SG) 1. Daran anschließend werden Untersuchungen zur mehrdimensionalen Mischung verschiedener Fluide, d.h. der Mischung des unterkühlten Wasserstroms und des Kühlmittels im Reaktordruckbehälter, betrachtet. Zu diesem Zweck werden die Randbedingungen aus dem Test PKL G3.1, der auf der PKL-Prüfanlage im Rahmen des OECD/PKL-II-Projekts durchgeführt wurde, in die Simulation als Anfangs- und Randbedingungen über die Nennwerte eines KONVOI-Reaktors übertragen. Die in den Simulationen erzielten Ergebnisse werden qualitativ mit geeigneten experimentellen Daten aus den PKL- und ROCOM-Testanlagen verglichen. Sie zeigen eine gute Übereinstimmung zwischen Simulation und Experiment.
References
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© 2019, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- GRS Code System AC2
- Technical Contributions/Fachbeiträge
- Development of AC2 for the simulation of advanced reactor design of Generation 3/3+ and light water cooled SMRs
- Thermal-hydraulic insights during a main steam line break in a generic PWR KONVOI reactor with ATHLET 3.1A
- Heat transfer to water near the critical point: evaluation of the ATHLET thermal-hydraulic system code
- ATHLET extensions for the simulation of supercritical carbon dioxide driven power cycles
- Validation of the AC2 Codes ATHLET and ATHLET-CD
- Comparative analysis of simulations of LIVE-L10 and -L11 experiments using different lower head modules of AC2
- Validation and Application of the AC2 Code COCOSYS
- Validation of COCOSYS 2.4v4 AIM module on various single effect and integral experiments
- Simulation of LOCA-typical containment conditions with COCOSYS on the basis of THAI-test TH-29.3
- Analysis of the melt spreading and MCCI during the ex-vessel phase of a severe accident in WWER-1000
- Technical Notes/Technische Mitteilungen
- New developments in the thermal hydraulic module THY of the COCOSYS program, part of the AC2 software package: turbulence in gaseous countercurrent flows
Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- GRS Code System AC2
- Technical Contributions/Fachbeiträge
- Development of AC2 for the simulation of advanced reactor design of Generation 3/3+ and light water cooled SMRs
- Thermal-hydraulic insights during a main steam line break in a generic PWR KONVOI reactor with ATHLET 3.1A
- Heat transfer to water near the critical point: evaluation of the ATHLET thermal-hydraulic system code
- ATHLET extensions for the simulation of supercritical carbon dioxide driven power cycles
- Validation of the AC2 Codes ATHLET and ATHLET-CD
- Comparative analysis of simulations of LIVE-L10 and -L11 experiments using different lower head modules of AC2
- Validation and Application of the AC2 Code COCOSYS
- Validation of COCOSYS 2.4v4 AIM module on various single effect and integral experiments
- Simulation of LOCA-typical containment conditions with COCOSYS on the basis of THAI-test TH-29.3
- Analysis of the melt spreading and MCCI during the ex-vessel phase of a severe accident in WWER-1000
- Technical Notes/Technische Mitteilungen
- New developments in the thermal hydraulic module THY of the COCOSYS program, part of the AC2 software package: turbulence in gaseous countercurrent flows
