Skip to main content

A Simulation-Based Dynamic Approach for External Flooding Analysis in Nuclear Power Plants

  • Conference paper
  • First Online:
Proceedings of The 20th Pacific Basin Nuclear Conference (PBNC 2016)

Included in the following conference series:

  • 807 Accesses

Abstract

All nuclear power plants must consider external flooding hazards such as local intense precipitation, riverine flooding, flooding due to upstream dam failure, and coastal flooding due to storm surge or tsunami. While external flooding events could potentially interrupt off-site power, threaten plant structures, systems and components important to safety, or limit plant access, they have often been qualitatively assessed as risk insignificant and screened out from detailed evaluation and quantification. Recent lessons learned from the Fukushima seismic/tsunami initiated nuclear accident (2011), the Fort Calhoun (2011), Vermont Yankee (2013), Arkansas Nuclear One (2013), and St. Lucie (2014) flooding events have highlighted the need for more detailed risk analysis. However, incorporating an external flood model into the traditional event tree/fault tree approach used in static probabilistic risk assessment (PRA) models is challenging because it is difficult to accurately represent plant system and component behavior and reliability of manual actions during an ever-progressing flood event. The plant response to external flood may be highly spatial and time dependent, subject to the hydrological and hydraulic characteristics of the flood event. Such unique challenges prompt the investigation of using simulation-based dynamic analysis approaches for external flood risk assessment. Simulation methods can better model the performance of structures, systems, and components during an external flooding event. A general framework to perform a simulation-based dynamic flooding analysis is presented in this paper with the subtasks of flood hazard analysis, flood fragility analysis, plant response modeling, safety margin analysis or PRA quantification. A new type of PRA technique, State-based PRA Modeling, is introduced to incorporate time-related interactions such as those from both 3D physical simulations and random failures into traditional PRA logic models.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 169.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 219.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. U.S. Nuclear Regulatory Commission, “Licensee Event Report 2011-003, Revision 3, for the Fort Calhoun Station,” U.S. Nuclear Regulatory Commission (2011).

    Google Scholar 

  2. U.S. Nuclear Regulatory Commission, “Licensee Event Report 2013-001, for the Vermont Yankee,” U.S. Nuclear Regulatory Commission (2013).

    Google Scholar 

  3. U.S. Nuclear Regulatory Commission, “Licensee Event Report 2013-001, Revision 1, for the Arkansas Nuclear One (ANO) Unit 1,” U.S. Nuclear Regulatory Commission (2013).

    Google Scholar 

  4. U.S. Nuclear Regulatory Commission, “Licensee Event Report 2014-001, Revision 3, for the St Lucie Unit 1,” U.S. Nuclear Regulatory Commission (2014).

    Google Scholar 

  5. U.S. Nuclear Regulatory Commission, “Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review Of Insights from the Fukushima Dai-Ichi Accident,” U.S. Nuclear Regulatory Commission (2011).

    Google Scholar 

  6. U.S. Nuclear Regulatory Commission, “Proceedings of the Workshop on Probabilistic Flood Hazard Assessment (PFHA),” U.S. Nuclear Regulatory Commission (2013).

    Google Scholar 

  7. J. Kanney, “NRC Probabilistic Flood Hazard Assessment Research Plan”, INL PFHA Projects Kickoff Meeting (2014).

    Google Scholar 

  8. C. Smith, D. Schwieder, C. Phelan, A. Bui, P. Bayless, “Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study,” Idaho National Laboratory INL/EXT-12-27015 (2012).

    Google Scholar 

  9. S. Prescott, R. Sampath, C. Smith, and T. Koonce, “Prototype Development Capabilities of 3D Spatial Interactions and Failures during Scenario Simulation,” Idaho National Laboratory INL/EXT-14-33211 (2014).

    Google Scholar 

  10. S. Prescott, C. Smith, T. Koonce, and T. Yang, “Case Study for Enhanced Accident Tolerance Design Changes,” Idaho National Laboratory INL/EXT-14-32355, Rev. 1 (2014).

    Google Scholar 

  11. C. Smith, D. Mandelli, S. Prescott, A. Alfonsi, C. Rabiti, J. Cogliati, and R. Kinoshita, “Analysis of Pressurized Water Reactor Station Blackout Caused by External Flooding Using the RISMC Toolkit,” Idaho National Laboratory INL/EXT-14-32906 (2014).

    Google Scholar 

  12. N. Akinci, M. Ihmsen, G. Akinci, B. Solenthaler and M. Teschner, “Versatile Rigid-Fluid Coupling for Incompressible SPH,” ACM Transactions on Graphics Proc. SIGGRAPH 2012, vol. 31, no. 4 (2014).

    Google Scholar 

  13. R. Sampath and S. Prescott, “Smooth Particle Hydrodynamics Approach for Advanced Flooding Analysis”.

    Google Scholar 

  14. R. Sampath, N. Akinci, S. Prescott, and C. Smith, “Implicit Incompressible Smoothed Particle Hydrodynamics Based Solitary Wave Simulation”.

    Google Scholar 

Download references

Acknowledgements

This work was supported by the U.S. Nuclear Regulatory Commission. We appreciate the insights and reviews provided by Joseph Kanney and Fernando Ferrante at NRC, as well the support from Ram Sampath at Centroid PIC.

Disclaimer

This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise, do not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Zhegang Ma .

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

© 2017 Springer Science+Business Media Singapore

About this paper

Cite this paper

Ma, Z., Smith, C., Prescott, S. (2017). A Simulation-Based Dynamic Approach for External Flooding Analysis in Nuclear Power Plants. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2311-8_6

Download citation

  • DOI: https://doi.org/10.1007/978-981-10-2311-8_6

  • Published:

  • Publisher Name: Springer, Singapore

  • Print ISBN: 978-981-10-2310-1

  • Online ISBN: 978-981-10-2311-8

  • eBook Packages: EnergyEnergy (R0)

Publish with us

Policies and ethics