The core shroud leakage analysis and study for Kuosheng nuclear power plant
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Abstract
Kuosheng Nuclear Power Plant (NPP) is a BWR/6 plant in Taiwan. First, this study focuses on the establishment of the TRACE/SNAP model for Kuosheng. To check the system response of the Kuosheng TRACE/SNAP model, the Final Safety Analysis Report (FSAR) and startup tests data are used to assess the TRACE/SNAP model. The TRACE predictions are consistent with the FSAR and startup tests data. This indicates that there is a respectable accuracy in the TRACE/SNAP model of Kuosheng NPP. Second, this study also focuses on the application of the TRACE/SNAP model in the core shroud leakage. The Kuosheng NPP TRACE/SNAP model is used to perform the analysis of core shroud leakage. The TRACE results imply that Kuosheng NPP is in a safe situation when the core shroud leakage transient occurs.
Kurzfassung
Das Kernkraftwerk Kuosheng (KKW) ist eine SWR/6-Anlage in Taiwan. Dieser Beitrag beschreibt die Erstellung eines TRACE/SNAP-Modells für Kuosheng. Zur Verifikation des Modells werden die Anfangs- und Randbedingungen des Final Safety Analysis Report (FSAR) und der Inbetriebnahmeprüfungen verwendet. Dabei zeigen die TRACE-Ergebnisse eine gute Übereinstimmung mit den Daten der FSAR- und Anlauftests. Dies deutet darauf hin, dass das TRACE/SNAP-Modell des KKW Kuosheng eine gute Genauigkeit aufweist. Im Anschluss daran wird ein Leck im Kern, d.h. in der Brennstoffhülle, abgebildet und berechnet mit dem TRACE/SNAP-Modell. Die so erzielten TRACE-Ergebnisse zeigen, dass sich bei diesen Transienten mit Lecks in der Brennstoffhülle das Kernkraftwerk Kuosheng immer in einem sicheren Anlagenzustand befindet.
References
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© 2019, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Revision of a CHF correlation for PWR under low pressure conditions with only dimensionless parameters as independent variables
- Experimental study on transient flow fluctuation characteristics in a 3 × 3 rod bundle under rolling condition
- The core shroud leakage analysis and study for Kuosheng nuclear power plant
- Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
- Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
- 10.3139/124.110984
- Control rod material effect on safety parameters of research reactors
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Revision of a CHF correlation for PWR under low pressure conditions with only dimensionless parameters as independent variables
- Experimental study on transient flow fluctuation characteristics in a 3 × 3 rod bundle under rolling condition
- The core shroud leakage analysis and study for Kuosheng nuclear power plant
- Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
- Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
- 10.3139/124.110984
- Control rod material effect on safety parameters of research reactors
