Abstract
The heat transfer coefficient is an essential measure in the predesign of supercritical water-cooled reactors (SCWRs). At supercritical pressures, three distinct heat transfer modes exist: normal, improved, and deteriorated. The heat transfer behavior of supercritical water in the pseudo-critical range is different from that of single-phase fluids in the subcritical range. These heat transfer modes differ from those of single-phase flow at subcritical pressures, resulting in an unusual behavior of the heat transfer coefficients. Moreover, during accidental scenarios, when the operating pressure is reduced from supercritical to subcritical conditions, a boiling crisis may occur. During pressure reduction, temporary phenomena such as superheating of the cladding temperature can endanger the safe operation of SCWRs. In order to analyze operational and accidental scenarios of SCWRs, thermal-hydraulic system codes such as ATHLET are applied. However, the prediction capabilities of thermal-hydraulic system codes rely on a comprehensive validation work based on experimental data. This study presents an extensive analysis of the applicability of ATHLET at the near-critical pressure range. ATHLET is assessed against the LESHP-database and two trans-critical transient experiments. At supercritical pressures, the heat transfer coefficient correlations are evaluated with regard to their prediction accuracy and numerical problems including the “multiple solutions problems”. The trans-critical transient experiments are used to test the prediction capability of ATHLET with respect to transient heat transfer phenomena including critical heat flux, film boiling and return to nucleate boiling.
Kurzfassung
Der Wärmeübergangskoeffizient ist essentiell bei der Auslegung von überkritischen wassergekühlten Reaktoren (SCWR) im Hinblick auf den Wärmeübergang im Reaktorkern. Das Wärmeübergangsverhalten von überkritischem Wasser weicht insbesondere im pseudo-kritischen Bereich vom typischen Wärmeübergangsverhalten einphasiger Fluide im unterkritischen Bereich ab. Im überkritischen Druckbereich untergliedert man das Wärmeübergangsverhalten deshalb in drei verschiedene Wärmeübertragungsbereiche: normal, verbessert und verschlechtert. Zudem kann bei Störfällen in SCWRs eine Druckabsenkung vom überkritischen in den unterkritischen Druckbereich erfolgen, die zu einer Siedekrise führt. Dabei können zeitlich begrenzte Phänomene wie eine Überhitzung der Rohrwand mit anschließender Wiederbenetzung auftreten. Um Betriebs- und Unfallszenarien von SCWRs zu analysieren, werden im Allgemeinen Thermohydraulik-Systemrechenprogramme wie ATHLET eingesetzt. Zur genauen Vorhersage sowie Validierung der Simulationsergebnisse stützen sich Thermohydraulik-Systemrechenprogramme auf die Ergebnisse experimenteller Untersuchungen. Entsprechend ist es Ziel dieser Studie, ATHLET im Hinblick auf den nah-kritischen Druckbereich zu testen. Dazu werden die Simulationsergebnisse mit der LESHP-Datenbank und zwei transienten Experimenten im transkritischen Druckbereich verglichen. Die überkritischen Wärmeübergangskorrelationen werden hinsichtlich ihrer Vorhersagegenauigkeit und der auftretenden numerischen Probleme einschließlich des Problems von Mehrfachlösungen untersucht. Die transkritischen transienten Experimente dienen dazu, die Anwendbarkeit der in ATHLET implementierten Modelle im Hinblick auf den kritischen Wärmestrom, Filmsieden und Rückkehr zum Blasensieden zu testen.
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