Abstract
The safe and secure designs of any nuclear power plant together with its cost-effective operation without accidents are leading the future of nuclear energy. As a result, the Reliability, Availability, Maintainability, and Safety analysis of NPP systems is the main concern for the nuclear industry. But the ability to assure that the safety-related system, structure, and components could meet the safety functions in different events to prevent the reactor core damage requires new reliability analysis methods and techniques. The Fault Tree Analysis (FTA) is one of the most widely used logic and probabilistic techniques in system reliability assessment nowadays. The Dynamic fault tree technique extends the conventional static fault tree (SFT) by considering the time requirements to model and evaluate the nuclear power plant safety systems. Thus this paper focuses on developing a new Dynamic Fault Tree for the Auxiliary Feed-water System (AFWS) in a pressurized water reactor. The proposed dynamic model achieves a more realistic and accurate representation of the AFWS safety analysis by illustrating the complex failure mechanisms including interrelated dependencies and Common Cause Failure (CCF). A Simulation tool is used to simulate the proposed dynamic fault tree model of the AFWS for the quantitative analysis. The more realistic results are useful to establish reliability cantered maintenance program in which the maintenance requirements are determined based on the achievement of system reliability goals in the most cost-effective manner.
Abstract
Die sichere Auslegung eines jeden Kernkraftwerks (KKW) zusammen mit seinem kostengünstigen Betrieb ohne Unfälle sind wegweisend für die Zukunft der Kernenergie. Daher ist die Analyse der Zuverlässigkeit, Verfügbarkeit, Instandhaltbarkeit und Sicherheit von Kernkraftwerken-Systemen das Hauptanliegen der Nuklearindustrie. Aber die Fähigkeit zu gewährleisten, dass das sicherheitsrelevante System, die Struktur und die Komponenten die Sicherheitsfunktionen bei verschiedenen Ereignissen erfüllen können, um die Beschädigung des Reaktorkerns zu verhindern, erfordert neue Methoden und Techniken der Zuverlässigkeitsanalyse. Die Fehlerbaumanalyse ist heutzutage eine der am meisten verwendeten logischen und probabilistischen Techniken in der Bewertung der Zuverlässigkeit von Systemen. Die dynamische Fehlerbaumtechnik erweitert den konventionellen statischen Fehlerbaum, indem sie die zeitlichen Anforderungen an die Modellierung und Bewertung der KKW-Sicherheitssysteme berücksichtigt. Diese Arbeit konzentriert sich auf die Entwicklung eines neuen dynamischen Fehlerbaums für das Auxiliary Feed-Water System (AFWS) in einem Druckwasserreaktor. Das vorgeschlagene dynamische Modell erreicht eine realistischere und genauere Darstellung der AFWSSicherheitsanalyse, indem es die komplexen Fehlermechanismen einschließlich der wechselseitigen Abhängigkeiten und Common Cause Failure abbildet. Ein Simulationswerkzeug wird verwendet, um das vorgeschlagene dynamische Fehlerbaumtechnik-Modell des AFWS für die quantitative Analyse zu simulieren. Die realistischeren Ergebnisse sind nützlich, um ein zuverlässigkeitsorientiertes Instandhaltungsprogramm zu erstellen, in dem die Instandhaltungsanforderungen auf der Grundlage der Erreichung der Systemzuverlässigkeitsziele auf eine sehr kosteneffektive Weise bestimmt werden.
Acknowledgements
The authors would like to express their gratitude for the advice and support given by Prof. Ferdinando Chiacchio of DIEEI, Department of Electrical, Electronic and Computer Engineering, University of Catania, Italy.
Nomenclature
- AFWS
auxiliary feed-water system
- CCF
common cause failure
- CST
condensate storage tank
- DFT
dynamic fault tree
- DPRA
dynamic probabilistic risk assessment
- ESFAS
engineered safety features actuation system
- ET
Event Trees
- FDEP
functional dependency gate
- FMEA
Failure Mode Effect Analysis
- FR
fails to run
- FS
fails to start
- FTA
fault tree analysis
- HFA
Human Factors Analysis
- LOCA
loss-of-coolant accident
- LOFW
Loss of Main Feedwater
- MDP
motor-driven pump
- MFWS
Main Feedwater System
- NPP
nuclear power plant
- PAND
priority AND gate
- PSA
Probabilistic Safety Assessments
- RAMS
reliability, availability, maintainability and safety
- SBO
station block out
- SEQ
sequence enforcing gate
- SFT
static fault tree
- SHyFTA
Stochastic Hybrid Fault Tree Automaton
- SPARE
spare gate
- TDP
steam turbine-driven pump
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