The analysis of fire ignition frequency calculation for small modular light water reactors
-
Hong Jiang
Abstract
With the release of reports such as NUREG/CR-6850, the calculation of ignition frequency concerning general large-scale Pressurized Water Reactors (PWRs) has matured. However, there is currently a lack of methods for calculating the ignition frequency in the case of Small Modular Light Water Reactors (SMRs). By studying the calculation of ignition frequency reported in NUREG/CR-6850, we propose a method for calculating the ignition frequency in SMRs, which is based on the generic ignition frequency at the component level. The problem of counting ignition sources is discussed in detail, and we determine the component-level ignition frequencies due to different types of ignition sources. In order to improve the calculation of the ignition frequency in SMRs, this paper provides two methods, which are based on the prior lognormal distribution and the prior Gamma distribution, respectively, for updating ignition frequency. We also consider the effect of the accumulation of fire events on the posterior mean determined by both methods. In this paper, we suggest that the method based on the prior lognormal distribution should be used in the initial stage of updates of ignition frequency. As data for plant-specific events accumulate, the approach based on the prior Gamma distribution should be considered.
-
Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
-
Research funding: None declared.
-
Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
References
Angner, A., Berg, H., Röwekamp, M., Werner, W., and Gauvain, J. (2007). The OECD FIRE database. Kerntechnik 72: 120–126, https://doi.org/10.3139/124.100327.Suche in Google Scholar
Arshi, S.S., Nematollahi, M., and Sepanloo, K. (2010). Coupling CFAST fire modeling and SAPHIRE probabilistic assessment software for internal fire safety evaluation of a typical TRIGA research reactor. Reliab. Eng. Syst. Saf. 95: 166–172, https://doi.org/10.1016/j.ress.2009.09.006.Suche in Google Scholar
Black, G.A., Aydogan, F., and Koerner, C.L. (2019). Economic viability of light water small modular nuclear reactors: general methodology and vendor data. Renew. Sustain. Energy Rev. 103: 248–258, https://doi.org/10.1016/j.rser.2018.12.041.Suche in Google Scholar
Cerotti, D., Gribaudo, M., and Bobbio, A. (2014). Markovian agents models for wireless sensor networks deployed in environmental protection. Reliab. Eng. Syst. Saf. 130: 149–158, https://doi.org/10.1016/j.ress.2014.05.010.Suche in Google Scholar
Chen, Y. and Yang, Z. (2021). Research on internal fire ignition frequency of fire probability safety analysis in small module reactor. Int. Conf. Nucl. Eng. 85260:V003T013A009, https://doi.org/10.1115/icone28-65152.Suche in Google Scholar
Jin, Y. and Jang, B.S. (2015). Probabilistic fire risk analysis and structural safety assessment of FPSO topside module. Ocean Eng. 104: 725–737, https://doi.org/10.1016/j.oceaneng.2015.04.019.Suche in Google Scholar
Jung, W.S., Lee, Y.H., and Yang, J.E. (2009). Development of a new quantification method for a fire PSA. Reliab. Eng. Syst. Saf. 94: 1650–1657, https://doi.org/10.1016/j.ress.2009.04.004.Suche in Google Scholar
Kim, S. and Lee, S. (2021). Maximum likelihood estimation of probabilistic non-suppression model for OECD NPP electrical fire applying non-negative continuous distribution. Fire Saf. J. 122: 103323, https://doi.org/10.1016/j.firesaf.2021.103323.Suche in Google Scholar
Kloos, M. and Peschke, J. (2015). Improved modelling and assessment of the performance of firefighting means in the frame of a fire PSA. Sci. Technol. Nucl. Install. 2015: 238723, https://doi.org/10.1155/2015/238723.Suche in Google Scholar
Lee, Y.H., Kim, J.H., and Yang, J.E. (2010). Application of the CFAST zone model to the Fire PSA. Nucl. Eng. Des. 240: 3571–3576, https://doi.org/10.1016/j.nucengdes.2010.04.035.Suche in Google Scholar
Najafi, B., Kassawara, R.P., Joglar-Biloch, F., and Khalil, Y. (2002). History of fire events in the US commercial nuclear industry. Int. Conf. Nucl. Eng. 35960: 381–388, https://doi.org/10.1115/ICONE10-22587.Suche in Google Scholar
Salvi, U., Lattimer, B.Y., Alhadhrami, S., Wang, J., Sahin, E., and Duarte, J.P. (2022). Analysis of historic fires to determine most frequent challenging events. Prog. Nucl. Energy 146: 104146, https://doi.org/10.1016/j.pnucene.2022.104146.Suche in Google Scholar
Schulz, T.L. (2006). Westinghouse AP1000 advanced passive plant. Nucl. Eng. Des. 236: 1547–1557, https://doi.org/10.1016/j.nucengdes.2006.03.049.Suche in Google Scholar
Shalabi, H. and Hadjisophocleous, G. (2018a). CANDU fire database. CNL Nucl. Rev. 8: 179–189, https://doi.org/10.12943/CNR.2017.00019.Suche in Google Scholar
Shalabi, H. and Hadjisophocleous, G. (2018b). CANDU fire probabilistic risk assessment (PRA) model. CNL Nucl. Rev. 8: 97–108, https://doi.org/10.12943/CNR.2017.00020.Suche in Google Scholar
© 2022 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions
- Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
- Updating risk model for SGTR accident based on success criteria analysis
- The analysis of fire ignition frequency calculation for small modular light water reactors
- New flow boiling frictional pressure drop multipliers for smooth and microfin tubes
- Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading
- Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers
- The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface
- Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions
- Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
- Updating risk model for SGTR accident based on success criteria analysis
- The analysis of fire ignition frequency calculation for small modular light water reactors
- New flow boiling frictional pressure drop multipliers for smooth and microfin tubes
- Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading
- Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers
- The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface
- Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Calendar of events
