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The evaluation of TRACE/PARCS model for BWR-4 nuclear power plant by startup test transient analyses

Bewertung des TRACE/PARCS-Modells für das Kernkraftwerk BWR-4 anhand instationärer Analysen des Anfahrversuchs
J.-J. Huang, S.-W. Chen, J.-R. Wang, C. Shih, H.-T. Lin and C.-K. Chen
From the journal Kerntechnik

Abstract

Generally, the thermal hydraulic (TH) codes need the results of Neutron Kinetics (NK) codes providing the reactivity properties to calculate neutron flux. Then the TH codes perform the safety analyses obtaining the responses of pressure, temperature, or water level. Two kinds of different codes calculate different physical behaviors sequentially and separately. Simultaneously computing thermal hydraulic and neutron kinetics behaviors can enhance the accuracy of the analysis. Hence, it is crucial to develop the TH-NK coupled model. This study presents the capability of the TH-NK coupled model, developed by TRACE (TRAC/RELAP Advanced Computational Engine) and PARCS (Purdue Advanced Reactor Core Simulator), for the BWR-4 nuclear power plant. The establishment of the TRACE/PARCS model presented the nodal and component modeling methodologies. This model was used to simulate two startup tests of high power level system transients. Principal system responses, calculated by the TRACE/PARCS model, were compared with the measured data in startup tests and the results of the point kinetic calculation of the TRACE (TRACE/PK) to evaluate the model. The evaluation shows that the TRACE/PARCS model can simulate the interaction between thermal hydraulic and neutron kinetics phenomena and predict the transients suitably. Through the comparison, the TRACE/PARCS model can be confident doing the analyses of normal and abnormal operational transients to predict the transient responses.

Abstract

Im Allgemeinen benötigen thermohydraulische (TH) Codes als Eingabedaten die Ergebnisse von Neutronenkinetik (NK) Codes, die die Reaktivitätseigenschaften zur Berechnung des Neutronenflusses liefern. Dann führen die TH-Codes die Sicherheitsanalysen durch, um die Parameter wie Druck, Temperatur oder Wasserstand zu berechnen. Zwei verschiedene Codes berechnen nacheinander und getrennt verschiedene physikalische Verhaltensweisen. Die gleichzeitige Berechnung des thermohydraulischen und neutronenkinetischen Verhaltens kann die Genauigkeit der Analyse verbessern. Daher ist es wichtig, ein gekoppeltes TH-NK-Modell zu entwickeln. In dieser Studie wird die Leistungsfähigkeit des gekoppelten TH-NK-Modells, das von TRACE (TRAC/RELAP Ad-vanced Computational Engine) und PARCS (Purdue Advanced Reactor Core Simulator) entwickelt wurde, für das Kernkraftwerk BWR-4 vorgestellt. Bei der Erstellung des TRACE/PARCS-Modells wurden die Methoden der Knoten- und Komponentenmodellierung vorgestellt. Dieses Modell wurde zur Simulation von zwei Anfahrversuchen mit Systemtransienten auf hohem Leistungsniveau verwendet. Die mit dem TRACE/PARCS-Modell berechneten Hauptreaktionen des Systems wurden mit den Messdaten der Anfahrversuche und den Ergebnissen der punktkinetischen Berechnung von TRACE (TRACE/PK) verglichen, um das Modell zu bewerten. Die Auswertung zeigt, dass das TRACE/PARCS-Modell die Wechselwirkung zwischen thermohydraulischen und neutronenkinetischen Phänomenen simulieren und die Transienten angemessen vorhersagen kann. Der Vergleich zeigt, dass das TRACE/PARCS-Modell bei der Analyse von normalen und anormalen Betriebstransienten zur Vorhersage der transienten Reaktionen zuverlässig ist.

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Received: 2021-02-01
Published Online: 2021-10-23

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