Abstract
This study aims to develop the Maanshan Pressurized Water Reactor (PWR) analysis model by using the TRACE (TRAC/RELAP Advanced Computational Engine) code. By analyzing the Large Break Loss of Coolant Accident (LBLOCA) sequence, the results are compared with the Maanshan Final Safety Analysis Report (FSAR) data. The critical flow and Counter Current Flow Limitation (CCFL) play an important role in the overall performance of TRACE LBLOCA prediction. Therefore, the sensitivity study on the discharge coefficients of critical flow model and CCFL modeling among different regions are also discussed. The current conclusions show that modeling CCFL in downcomer has more significant impact on the peak cladding temperature than modeling CCFL in hot-legs does. No CCFL phenomena occurred in the pressurizer surge line. The best value for the multipliers of critical flow model would be 0.5 and the TRACE could consistently predict the break flow rate in the LBLOCA analysis as shown in FSAR.
Kurzfassung
Für das Kernkraftwerk Maanshan vom Typ DWR wurde und werden Sicherheitsuntersuchungen mit dem Programm TRACE (TRAC/RELAP Advanced Computational Engine) durchgeführt. In diesem Beitrag werden Ergebnisse von Berechnungen grosser Brüche (LBLOCA) unter besonderer Berücksichtigung der Gegenstrombegrenzung (CCFL) und der kritischen Strömung vorgestellt. Die Ergebnisse dieser aktuellen Berechnungen werden mit den Daten aus dem Maanshan Sicherheitsbericht (FSAR) verglichen. Dabei zeigt sich, dass die Berücksichtigung von CCFL im Downcomer einen stärkeren Einfluss auf die maximale Hüllrohrtemperatur hat als die Berücksichtigung des CCFL in den heißen Strängen. In der Surge Line werden keine CCFL-Phänomene beobachtet.
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