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

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

doi:10.3850/978-981-11-2724-3_0536-cd

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

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

Metallurgy and Materials

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

2 Citations (Scopus)

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.

Original language	English
Title of host publication	Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019
Editors	Michael Beer, Enrico Zio
Publisher	Research Publishing Services
Pages	3831-3838
Number of pages	8
ISBN (Electronic)	9789811127243
DOIs	https://doi.org/10.3850/978-981-11-2724-3_0536-cd
Publication status	Published - 2020
Event	29th European Safety and Reliability Conference, ESREL 2019 - Hannover, Germany Duration: 22 Sept 2019 → 26 Sept 2019

Publication series

Name	Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019

Conference

Conference	29th European Safety and Reliability Conference, ESREL 2019
Country/Territory	Germany
City	Hannover
Period	22/09/19 → 26/09/19

Bibliographical note

Funding Information:
Gratitude is expressed to EPSRC for their financial support of the DaMSSLE project, reference code EP/M018210/1. Additional thanks go to Andrey Vasilyev for useful conversations regarding the Modelica modelling language and the BondLib package.

Publisher Copyright:
© 2019 European Safety and Reliability Association. Published by Research Publishing, Singapore.

Keywords

Bond Graphs Modeling
Coupled PN-BG Modeling
Nuclear Power Plants
Nuclear Reactor Coolant Circlation
Petri Net Modeling
Risk and Reliability Engineering

ASJC Scopus subject areas

Safety, Risk, Reliability and Quality
Safety Research

Access to Document

10.3850/978-981-11-2724-3_0536-cd

Cite this

Wootton, M. J., Andrews, J., Lloyd, A. L., Smith, R., John Arul, A., Vinod, G., Prasad, S. H., & Garg, V. (2020). 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 (pp. 3831-3838). (Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019). Research Publishing Services. https://doi.org/10.3850/978-981-11-2724-3_0536-cd

Wootton, Mark James ; Andrews, John ; Lloyd, Adam L. et al. / Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system. Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019. editor / Michael Beer ; Enrico Zio. Research Publishing Services, 2020. pp. 3831-3838 (Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019).

@inproceedings{c3b579c550814368983b79ed3c14ae50,

title = "Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system",

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.",

keywords = "Bond Graphs Modeling, Coupled PN-BG Modeling, Nuclear Power Plants, Nuclear Reactor Coolant Circlation, Petri Net Modeling, Risk and Reliability Engineering",

author = "Wootton, {Mark James} and John Andrews and Lloyd, {Adam L.} and Roger Smith and {John Arul}, A. and Gopika Vinod and Prasad, {Shri Hari} and Vipul Garg",

note = "Funding Information: Gratitude is expressed to EPSRC for their financial support of the DaMSSLE project, reference code EP/M018210/1. Additional thanks go to Andrey Vasilyev for useful conversations regarding the Modelica modelling language and the BondLib package. Publisher Copyright: {\textcopyright} 2019 European Safety and Reliability Association. Published by Research Publishing, Singapore.; 29th European Safety and Reliability Conference, ESREL 2019 ; Conference date: 22-09-2019 Through 26-09-2019",

year = "2020",

doi = "10.3850/978-981-11-2724-3_0536-cd",

language = "English",

series = "Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019",

publisher = "Research Publishing Services",

pages = "3831--3838",

editor = "Michael Beer and Enrico Zio",

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Wootton, MJ, Andrews, J, Lloyd, AL, Smith, R, John Arul, A, Vinod, G, Prasad, SH & Garg, V 2020, 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. Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019, Research Publishing Services, pp. 3831-3838, 29th European Safety and Reliability Conference, ESREL 2019, Hannover, Germany, 22/09/19. https://doi.org/10.3850/978-981-11-2724-3_0536-cd

Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system. / Wootton, Mark James; Andrews, John; Lloyd, Adam L. et al.
Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019. ed. / Michael Beer; Enrico Zio. Research Publishing Services, 2020. p. 3831-3838 (Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

TY - GEN

T1 - Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system

AU - Wootton, Mark James

AU - Andrews, John

AU - Lloyd, Adam L.

AU - Smith, Roger

AU - John Arul, A.

AU - Vinod, Gopika

AU - Prasad, Shri Hari

AU - Garg, Vipul

N1 - Funding Information: Gratitude is expressed to EPSRC for their financial support of the DaMSSLE project, reference code EP/M018210/1. Additional thanks go to Andrey Vasilyev for useful conversations regarding the Modelica modelling language and the BondLib package. Publisher Copyright: © 2019 European Safety and Reliability Association. Published by Research Publishing, Singapore.

PY - 2020

Y1 - 2020

N2 - 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.

AB - 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.

KW - Bond Graphs Modeling

KW - Coupled PN-BG Modeling

KW - Nuclear Power Plants

KW - Nuclear Reactor Coolant Circlation

KW - Petri Net Modeling

KW - Risk and Reliability Engineering

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SP - 3831

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BT - Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019

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PB - Research Publishing Services

T2 - 29th European Safety and Reliability Conference, ESREL 2019

Y2 - 22 September 2019 through 26 September 2019

ER -

Wootton MJ, Andrews J, Lloyd AL, Smith R, John Arul A, Vinod G et al. Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system. In Beer M, Zio E, editors, Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019. Research Publishing Services. 2020. p. 3831-3838. (Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019). doi: 10.3850/978-981-11-2724-3_0536-cd

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

Abstract

Publication series

Conference

Bibliographical note

Keywords

ASJC Scopus subject areas

Access to Document

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Cite this