[PDF][PDF] Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system

MJ Wootton, J Andrews, AL Lloyd, R Smith… - Proceedings of the …, 2019 - academia.edu
MJ Wootton, J Andrews, AL Lloyd, R Smith, AJ Arul, G Vinod, SH Prasad, V Garg
Proceedings of the 29th European Safety and Reliability Conference, 2019academia.edu
In this paper we demonstrate the application of timed Petri Net methodology to the frequency
of initiating faults in the coolant circulation system of a fictional nuclear reactor design. A
second model is presented where the Petri Net is coupled with a Bond Graph representation
of reactor thermodynamics, and distributions of temperatures reached by core coolant and
fuel cladding during component failures is produced.
In this paper we demonstrate the application of timed Petri Net methodology to the frequency of initiating faults in the coolant circulation system of a fictional nuclear reactor design. A second model is presented where the Petri Net is coupled with a Bond Graph representation of reactor thermodynamics, and distributions of temperatures reached by core coolant and fuel cladding during component failures is produced.
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