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Licensed Unlicensed Requires Authentication Published by De Gruyter March 30, 2021

Methodology for integral analysis of ATWS for Kuosheng nuclear power station

Integrale Analyse eines ATWS Szenarios für das Kernkraftwerk Kuosheng
H.-C. Chien, K.-H. Jsu, A.-S. Lin, H.-T. Lin and C. T. Lin
From the journal Kerntechnik


An integral analysis methodology for BWR ATWS has been developed. The method covers main scopes about ATWS events, including radiological consequence, primary system integrity, fuel integrity, containment integrity, and long-term shutdown and cooling capability. The primary techniques about this methodology were described herein. The methodology has been applied on Kuosheng nuclear power station to show the applicability. Under this framework, some suggestions were proposed for further development of this methodology. This methodology can give a way to evaluate safety of BWR plants confidently. Further, it can be a tool for developing emergency procedures about severe accidents, or exploring strategies and checking their effectiveness.


Es wurde eine integrale Analysemethodik zur Berechnung eines ATWS Ereignisses in einem Siedewasserreaktor entwickelt. Die Methode deckt die Hauptbereiche von ATWS-Ereignissen ab, einschließlich der radiologischen Folgen, der primären Systemintegrität, der Brennstoffintegrität, der Containmentintegrität und der langfristigen Abschalt- und Kühlfähigkeit. Die wesentlichen Techniken dieser Methodik werden in diesem Beitrag zusammengefasst.

Die Anwendbarkeit dieser Methodik wird durch die Beschreibung der Berechnung für ein ATWS am Kernkraftwerk Kuosheng gezeigt. In diesem Rahmen werden einige Vorschläge für die weitere Entwicklung dieser Methodik gemacht. Diese Methodik kann als Werkzeug zur zuverlässigen Bewertung der Sicherheit von SWR-Anlagen dienen. Außerdem kann sie bei der Entwicklung von Notfallprozeduren für schwere Unfälle oder der Erforschung von Strategien und deren Überprüfung eingesetzt werden.



anticipated operation occurrence


alternate rod injection


anticipated transient without scram


beginning of cycle


boiling water reactor


critical heat flux


critical power ratio


design basis accident


decay ratio


exclusion area boundary


experimental critical power ratio


end of cycle


general electric company


institute of nuclear energy research


local power peaking factor


low population zone


middle of cycle


main steam isolation valve closure


measurement uncertainty recapture


Nuclear Steam Supply System


operating critical power ratio


peach bottom turbine trip


peak cladding temperature


probability density function


pressure regulator failure open


reactor coolant pressure boundary


rector core isolation cooling


residual heat removal


reactor protection system


recirculating pump trip


reactor pressure vessel


redundant reactivity control system


standby gas treatment system


standby liquid control system


safety limit minimum critical power ratio


stretch power uprate


Taiwan power company


turbine trip


turbine trip with bypass


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Received: 2020-09-28
Published Online: 2021-03-30
Published in Print: 2021-04-30

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