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Research Article

An integrated Petri net-pseudo bond graph model for nuclear hazard assessment

ORCID Icon, ORCID Icon, ORCID Icon, ORCID Icon, ORCID Icon, & ORCID Icon show all
Received 26 Apr 2023, Accepted 30 May 2024, Published online: 01 Aug 2024

References

  • Aldemir, T. (2013). A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants. Annals of Nuclear Energy, 52, 113–124. https://doi.org/10.1016/j.anucene.2012.08.001
  • Allard, B., Helali, H., Lin, C.-C., & Morel, H. (1995). Power Converter Average Model Computation using the Bond Graph and Petri Net Techniques. In Ieee pesc (pp. 830–836). https://doi.org/10.1109/pesc.1995.474913
  • Allard, B., Morel, H., & Chante, J.-P. (1993). Power electronic circuit simulation using bond graph and Petri network techniques. In Proceedings of IEEE Power Electronics Specialist conference - PESC'93. https://doi.org/10.1109/PESC.1993.471933
  • Andersson, C., Åkesson, J., & Führer, C. (2016). PyFMI: A Python Package for Simulation of Coupled Dynamic Models with the Functional Mock-up Interface. Technical Report in Mathematical Sciences, 2016(2). https://portal.research.lu.se/en/publications/pyfmi-a-python-package-for-simulation-of-coupled-dynamic-models-w
  • Andrews, J. D., & Dunnett, S. J. (2000). Event-tree analysis using binary decision diagrams. IEEE Transactions on Reliability, 49(2), 230–238. https://doi.org/10.1109/24.877343
  • Badoud, A., Khemliche, M., & Latreche, S. (2009). Modeling, simulation and monitoring of nuclear reactor using directed graph and bond graph. International Journal of Computer and Systems Engineering, 3(1), 71–80.
  • Balbo, G. (2007). Introduction to Generalized Stochastic Petri Nets. In M. Bernardo & J. Hillston (Eds.), Formal Methods for Performance Evalutation – 7th International School on Formal Methods for the Design of Computer, Communication and Software Systems, SFM 2007., may/june 2007, advanced lectures, lecture notes in computer science (Vol. 4486, pp. 83–131). Springer.
  • Barringer & Associates, Inc. (2010). (Last edited: Weibull Reliability Database For Failure Data For Various Components. www.barringer1.com/wdbase.htm Accessed November 2018.
  • Bentaleb, T., Pham, M. T., Eberard, D., & Marquis-Favre, W. (2018). Bond graph modeling and analysis of intermediary cooling system of a nuclear power plants [Paper presentation]. 2018 Ieee International Conference on Industrial Technology (Icit), (pp. 93–98). https://doi.org/10.1109/icit.2018.8352158
  • Borutzky, W., Dauphin-Tanguy, G., & Thoma, J. U. (1995). Advances in bond graph modelling: theory, software, applications. Mathematics and Computers in Simulation, 39(5–6), 465–475. https://doi.org/10.1016/0378-4754(95)00106-6
  • Bouhalouane, M., Larbi, S., & Haffaf, H. (2015). Combining bond graphs and petri nets formalism for modelinghybrid dynamic systems. In The 10th International Conference on Future Networks and Communications (Fnc 2015), Procedia Computer Science (Vol. 56, pp. 252–259.). https://www.sciencedirect.com/science/article/pii/s1877050915016865
  • Bouhalouane, M., Sekhri, L., & Haffaf, H. (2020). On extending transitions logic in hybrid dynamic systems based on bond graph and Petri nets combination. International Journal of System of Systems Engineering, 10(1), 1–23. https://doi.org/10.1504/ijsse.2020.105421
  • Brînzei, N., & Aubry, J.-F. (2018). Graphs models and algorithms for reliability assessment of coherent and non-coherent systems. Proceedings of the Institution of Mechanical Engineers, Part O: Journal of Risk and Reliability, 232(2), 201–215. https://doi.org/10.1177/1748006X17744381
  • Cellier, F. E., & Nebot, À. (2005). The Modelica Bond Graph Library. In Proceedings of the 4th International Modelica Conference, Hamburg (pp. 57–65).
  • Clarke, G. M., & Cooke, D. (1978). A Basic Cource in Statistics. (2004, 5th ed.). John Wiley & Sons Ltd.
  • Dennis, B., & Patil, G. P. (1987). Lognormal Distributions, Theory and Applications. In E. L. Crow & K. Shimizu, Eds. Marcel Dekker.
  • Eide, S. A., & Calley, M. B. (1993). Generic component failure database. Proceedings of PSA International Topical Meeting pp 1175, 2.
  • Eide, S. A., Chmielewski, S. V., & Swantz, T. O. (1990). Generic Component Failure Data Base for Light Water and Liquid Sodium Reactor PRAs. Idaho National Engineering Laboratory. https://www.osti.gov/biblio/10117849
  • Ekanayake, T., Dewasurendra, D., Abeyratne, S., Ma, L., & Yarlagadda, P. (2019). Model-based fault diagnosis and prognosis of dynamic systems: a review. Procedia Manufacturing, 30, 435–442. https://doi.org/10.1016/j.promfg.2019.02.060
  • Energy and light. (2008). The Open University. (p.179)
  • Fritzson, P., & Engelson, V. (1998). Modelica – A unified object-oriented language for system modeling and simulation. Jul E. (ed) ECOOP’98 – Object-Oriented Programming. ECOOP 1998. Lecture Notes in Computer Science, 1445.
  • Holman, J. P. (1990). Heat Transfer. (2010, 10th ed.). McGraw-Hill Higher Education.
  • IAEA. (1988). IAEA-TECDOC-478 Component Reliability Data for Use in Probabilistic Safety Assessment. (Tech. Rep.). International Atomic Energy Agency.
  • Incropera, F. P., & de Witt, D. P. (1990). Fundamentals of Heat and Mass Transfer. Wiley.
  • Jiang, R., & Murthy, D. N. P. (2011). A study of Weibull shape parameter: Properties and significance. Reliability Engineering & System Safety, 96(12), 1619–1626. https://doi.org/10.1016/j.ress.2011.09.003
  • Jyotish, N. K., Singh, L. K., & Kumar, C. (2022). A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP. Annals of Nuclear Energy, 165, 108635. https://doi.org/10.1016/j.anucene.2021.108635
  • Kachur, S. A., & Shakhova, N. V. (2016). Turbine generator status diagnostic system based on petri nets. Nuclear Energy and Technology, 2(2), 81–84. https://doi.org/10.1016/j.nucet.2016.05.002
  • Karnopp, D. (1978). Pseudo bond graphs for thermal energy transport. Journal of Dynamic Systems, Measurement, and Control, 100(3), 165–169. https://doi.org/10.1115/1.3426363
  • Kumar, P., Singh, L. K., & Kumar, C. (2019). Performance evaluation of safety-critical systems of nuclear power plant systems. Nuclear Engineering and Technology, 52(3), 560–567. https://doi.org/10.1016/j.net.2019.08.018
  • Lee, S. J., & Seong, P. H. (2004). Development of automated operating procedure system using fuzzy colored petri nets for nuclear power plants. Annals of Nuclear Energy, 31(8), 849–869. https://doi.org/10.1016/j.anucene.2003.12.002
  • Metropolis, N., & Ulam, S. (1949). The Monte Carlo method. Journal of the American Statistical Association, 44(247), 335–341. https://doi.org/10.1080/01621459.1949.10483310
  • Michel, P., Maschke, B., & Manesse, G. (1993). Bond-Graph Enumeration of the Configurations of Power Static Converters [Paper presentation]. International Conference on Systems, Man and Cybernetics, In Proceedings of IEEESystems Man and Cybernetics Conference - SMC, Le Touquet, France, 1993, (Vol. 1, pp. 251–256). https://ieeexplore.ieee.org/document/384753
  • Miller, C. F., W. H., Hubble, M. T., & Brown, S. R. (1982). Data summaries of Licensee Event Reports of valves at US commercial nuclear power plants: January 1, 1976 to December 31, 1980 (Tech. Rep.).– Prepared for U.S. Nuclear Regulatory Commission. EG and G Idaho, Inc.
  • Mokhtar, B., & Hafid, H. (2012). An hybrid Bond Graph approach using Petri Net [Paper presentation].16th IEEE Mediterranean Electrotechnical Conference, 438–441. https://ieeexplore.ieee.org/document/6196467
  • Morris, S. (2019). Failure Rate Estimates for Mechanical Components. www.reliabilityanalyticstoolkit.appspot.com/mechanical_reliability_data
  • Németh, E., Bartha, T., Fazekas, C., & Hangos, K. M. (2009). Verification of a primary-to-secondary leaking safety procedure in a nuclear power plant using coloured Petri nets. Reliability Engineering & System Safety, 94(5), 942–953. https://doi.org/10.1016/j.ress.2008.10.012
  • Papoulis, A., & Pillai, S. U. (2002). Probability, Random Variables and Stochastic Processes. (4th ed.; C. F. Shultz & M. L. Flomenhoft, Eds.). McGraw Hill.
  • Paynter, H. M. (1961). Analysis and Design of Engineering Systems. The M.I.T. Press.
  • Petri, C. A. (1962). Kommunikation mit Automaten. (Unpublished doctoral dissertation) Technical University Darmstadt.
  • Pettersson, S., & Lennartson, B. (1995). Hybrid Modelling focused on Hybrid Petri Nets. In 2nd european workshop on real-time and hybrid systems (pp. 303–309).
  • Ponciroli, R., Cammi, A., Lorenzi, S., & Luzzi, L. (2016). Petri-net based modelling approach for ALFRED reactor operation and control system design. Progress in Nuclear Energy, 87, 54–66. https://doi.org/10.1016/j.pnucene.2015.10.009
  • Popov, S. G., Carbajo, J. J., Ivanov, V. K., & Yonder, G. L. (2000). Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation. (Tech. Rep. No. ORNL/TM-2000/351). Fissile Materials Disposition Program, Oak Ridge National Laboratory.
  • PubChem. (2020, Februrary). Uranium dioxide. U.S. National Library of Medicine National Center for Biotechnology Information www.pubchem.ncbi.nlm.nih.gov/compound/Uranium-dioxide
  • Rasmussen, N. C. (1975). Reactor safety study: An assessment of accident risks in US commercial nuclear power plants (WASH-1400) (Tech. Rep.). US Nuclear Regulatory Commission.
  • Reliability Eta Beta database. (2020, January (www.reliabilityetabeta.com)).
  • Schneeweiss, W. G. (2004). Petri Net Picture Book (an Elementary Introduction to the Best Pictorial Description of Temporal Changes). LiLoLe – Verlag GmbH (Publ. Co. Ltd.).
  • Singh, L., & Rajput, H. (2016). Safety analysis of life critical software systems: a case study of nuclear power plant. IETE Technical Review, 34(3), 333–339. https://doi.org/10.1080/02564602.2016.1190305
  • Singh, L. K., Vinod, G., & Tripathi, A. K. (2016). Early prediction of software reliability: A case study with a nuclear power plant system. Computer Magazine, 49(1), 52–58. https://doi.org/10.1109/mc.2016.15
  • Sinha, R. K., & Kakodkar, A. (2006). Design and development of the AHWR – the Indian thorium fueld innovative nuclear reactor. Nuclear Engineering and Design, 236(7-8), 683–700. https://doi.org/10.1016/j.nucengdes.2005.09.026
  • Smith, D. J. (1981). Reliability, Maintainability and Risk. Practical Methods for Engineers including Reliability Centred Maintenance and Safety-Related Systems. (2005, 7th edition ed.). Elsevier Butterworth-Heinemann.
  • Sosnovsky, E., & Forget, B. (2013). Bond graphs for spatial kinetics analysis of nuclear reactors. Annals of Nuclear Energy, 56, 208–226. https://doi.org/10.1016/j.anucene.2013.01.012
  • Sosnovsky, E., & Forget, B. (2014). Bond graph representation of nuclear reactor point kinetics and nearly incompressible thermal hydraulics. Annals of Nuclear Energy, 68, 15–29. https://doi.org/10.1016/j.anucene.2013.12.013
  • Terrani, K. A., Zinkle, S. J., & Snead, L. L. (2014). Advanced oxidation-resistant iron-based alloys for LWR fuel cladding. Journal of Nuclear Materials, 448(1–3), 420–435. https://doi.org/10.1016/j.jnucmat.2013.06.041
  • United States Nuclear Regulatory Commission. (2021, October). (Last edited: § 50.46 Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors.) www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-0046.html .
  • Vasilyev, A., Andrews, J., Jackson, L., Dunnett, S., & Davies, B. (2017). Component-based modelling of PEM fuel cells with bond graphs. International Journal of Hydrogen Energy, 42(49), 29406–29421. https://doi.org/10.1016/j.ijhydene.2017.09.004
  • Vesely, W. E. (1970). A time-dependent methodology for fault tree evaluation. Nuclear Engineering and Design, 13(2), 337–360. https://doi.org/10.1016/0029-5493(70)90167-6
  • Watson, H. A. (1961). Launch control safety study. (Tech. Rep.). Bell Labs.
  • Whitelaw, J. H. (2011). (Last edited: CONVECTIVE HEAT TRANSFER. www.thermopedia.com/es/content/660/ Accessed February 2018.
  • Whitmarsh, C. L. (1962). Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design (Tech. Rep. Nos. ORNL-3281 UC-80 – Reactor Technology TID-4500). Oak Ridge National Laboratory. (17th edition)
  • Wootton, M. J., Andrews, J., Lloyd, A. L., Smith, R., Arul, A. J., Vinod, G., Prasad, S.H., Garg, V. (2019). Petri nets and pseudo-bond graphs for a nuclear reactor primary coolant system. Proceedings of the 29th European Safety and Reliability Conference, 3831–3839.
  • Wootton, M. J., Andrews, J. D., Lloyd, A. L., Smith, R., Arul, A. J., Vinod, G., Prasad, M. H., & Garg, V. (2022). Risk modelling of ageing nuclear reactor systems. Annals of Nuclear Energy, 166, 108701. https://doi.org/10.1016/j.anucene.2021.108701
  • Xu, H., & Dugan, J. B. (2004). Combining dynamic fault trees and event trees for probabilistic risk assessment. In Annual Symposium Reliability and Maintainability, 2004 - RAMS. IEEE. pp. 214–219. https://ieeexplore.ieee.org/document/1285450
  • Zanzouri, N., & Tagina, M. (2002). A comparative study of hybrid system monitoring based on bond graph and petri net modelling. In Ieee International Conference on Systems, Man and Cybernetics (Vol. 4, pp. 6.). https://ieeexplore.ieee.org/document/1173226
  • Zhou, Z., Ma, Z., Jiang, Y., & Peng, M. (2022). Fault diagnosis using bond graphs in an expert system. Energies, 15(15), 5703. https://doi.org/10.3390/en15155703
  • Zimmer, D., & Cellier, F. E. (2006). The modelica multi-bond graph library. In Proceedings of the 5th International Modelica Conference (pp. 559–568.). https://www.semanticscholar.org/paper/the-modelica-multi-bond-graph-library-zimmer-cellier/91fafc9f858b4ee487df4ee326946cdcc98eaba8