Abstract
In this research, TRACE code with the interface SNAP was used to evaluate and simulate the postulated Extended Loss of AC Power (ELAP) accident in Maanshan Nuclear Power Plant (NPP). This study is to determine whether Reactor Coolant System (RCS) water level will be below Top of Active Fuel (TAF) while the 5th diesel generator and gas turbines are all disabled when the accident occurred. The scenario and assumptions of postulated ELAP in this research are referred to the WCAP-17601-Pt and NUREG-1953 reports. Additionally, this study will run a base case without any mitigation strategy and four cases with multiple mitigation strategies to analyze the effectiveness of URG and FLEX strategies. According to the analysis results of TRACE, it can be found that all four cases with mitigation strategies can keep RCS water level above TAF. This indicates that URG and FLEX strategies can ensure the safety function of reactor.
Kurzfassung
In diesem Beitrag wurde der TRACE code mit der Schnittstelle SNAP verwendet, um den postulierten Extended Loss of AC Power (ELAP)-Unfall im Kernkraftwerk Maanshan (NPP) auszuwerten und zu simulieren. Diese Studie soll bestimmen, ob der Wasserstand des Reactor Coolant System (RCS) unter dem Top of Active Fuel (TAF) liegt, während der 5. Dieselgenerator und die Gasturbinen bei dem Unfall deaktiviert sind. Das Szenario und die Annahmen des postulierten ELAP beziehen sich auf die Berichte WCAP-17601-Pt und NUREG-1953. Zusätzlich wird in dieser Studie ein Basisfall ohne Minderungsstrategie und vier Fälle mit mehreren Minderungsstrategien zur Analyse der Wirksamkeit von URG- und FLEX-Strategien durchgeführt. Nach den Analyseergebnissen von TRACE lässt sich feststellen, dass alle vier Fälle mit Minderungsstrategien den RCS-Wasserstand über TAF halten können. Dies zeigt, dass URG- und FLEX-Strategien die Sicherheitsfunktion des Reaktors gewährleisten können.
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