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

Wootton, Mark James; Andrews, John; Lloyd, Adam L.; Smith, Roger; Arul, A. John; Vinod, Gopika; Prasad, Shri Hari; Garg, Vipul

Authors

Mark James Wootton

John Andrews

Adam L. Lloyd

Roger Smith

A. John Arul

Gopika Vinod

Shri Hari Prasad

Vipul Garg



Contributors

Michael Beer
Editor

Enrico Zio
Editor

Abstract

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.

Start Date Sep 22, 2019
Publication Date Sep 24, 2019
Pages 3831-3839
Book Title Proceedings of the 29th European Safety and Reliability Conference (ESREL 2019)
APA6 Citation Wootton, M. J., Andrews, J., Lloyd, A. L., Smith, R., Arul, A. J., Vinod, G., …Garg, V. (2019). Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system. In M. Beer, & E. Zio (Eds.), Proceedings of the 29th European Safety and Reliability Conference (ESREL 2019), 3831-3839. https://doi.org/10.3850/978-981-11-2724-3_+0536-cd
DOI https://doi.org/10.3850/978-981-11-2724-3_+0536-cd
Keywords Risk and reliability engineering, Nuclear power plants, Petri net modeling, Bond graphs Modeling,
Publisher URL http://itekcmsonline.com/rps2prod/esrel2019/e-proceedings/html/0536.xml
Related Public URLs https://esrel2019.org/#/

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