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

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.

Citation

Wootton, M. J., Andrews, J., Lloyd, A. L., Smith, R., Arul, A. J., Vinod, G., Prasad, S. H., & Garg, V. (2019, September). Petri Nets and Pseudo-Bond Graphs for a Nuclear Reactor Primary Coolant System. Presented at 29th European Safety and Reliability Conference (ESREL 2019), Hannover, Germany

• Presentation Conference Type: Edited Proceedings
• Conference Name: 29th European Safety and Reliability Conference (ESREL 2019)
• Start Date: Sep 22, 2019
• End Date: Sep 26, 2019
• Acceptance Date: Apr 8, 2019
• Publication Date: 2019
• Deposit Date: Jun 21, 2019
• Publicly Available Date: Jun 21, 2019
• Pages: 3831-3838
• Book Title: Proceedings of the 29th European Safety and Reliability Conference (ESREL 2019)
• 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,
• Public URL: https://nottingham-repository.worktribe.com/output/2216544
• Publisher URL: http://rpsonline.com.sg/proceedings/9789811127243/html/0536.xml
• Related Public URLs: https://esrel2019.org/#/
• Contract Date: Jun 21, 2019