Skip to main content

An Overview of Severe Accident Approach at EDF—Contribution of R&D Programs

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

Included in the following conference series:

  • 821 Accesses

Abstract

The need for improving knowledge and designing mitigation measures in the field of severe accidents emerged particularly after the Three Mile Island 2 accident. Since the 80s EDF has undertaken, together with its French R&D partners (CEA, IRSN, AREVA), its own R&D programs covering over time nearly all areas related to core melt accidents. EDF also relies on international collaborations with several laboratories, and participates in international programs, either supported by the European Commission or those conducted in the framework of the OECD. This paper gives an overview of the severe accident approach at EDF from an R&D point of view. The phenomena covered are steam explosion, hydrogen combustion, direct containment heating (DCH), slow containment pressurization, basemat penetration. The risks associated with these phenomena in a nuclear power plant and some examples of industrial implementations of mitigation measures, based on engineering and R&D outcomes, are presented.

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. Atkhen K. Spindler B. “Use of MCCI-OECD Projects and CCI French R&D program for reactor applications and future needs to reduce remaining uncertainties”, MCCI Seminar 2010, 15th–17th November 2010, Cadarache, France.

    Google Scholar 

  2. Azizian R., McKrell, T., Buongiorno J., Atkhen K. «Effects of Porous Superhydrophilic Surfaces on Flow Boiling Critical Heat Flux in IVR, NURETH-16, Chicago, 2015.

    Google Scholar 

  3. Basu S., Buck M., Leskovar M., Meignen R., Nitheananban T., Piluso P., Hong S.-W. «OECD/SERENA integrated report (Steam Explosion Resolution for Nuclear Applications)», 2014.

    Google Scholar 

  4. Gravilas M., Farmer M. “MCCI-2 Program Overview” MCCI Seminar 2010, 15th–17th November 2010, Cadarache, France.

    Google Scholar 

  5. Jamet M., Lavieville, J., Atkhen K., Méchitoua N. «Validation of NEPTUNE_CFD on ULPU-V experiments», Nuclear Engineering and Design, Volume 293, November 2015, Pages 468–475.

    Google Scholar 

  6. Méchitoua N., Mimouni, S. “Numerical Assessment of PANDA Experiments covering Steam/Air/Helium Mixtures”, NURETH-14, Toronto, Ontario, Canada, September 2011.

    Google Scholar 

  7. Mimouni.S, A. Foissac, J. Lavieville, “CFD modelling of wall steam condensation by a two-phase flow approach”, Nuclear Engineering and Design, Volume 241, Issue 11, November 2011, Pages 4445–4455.

    Google Scholar 

  8. Miassaedov A., Meyer L. “Early Containment Failure - Direct Containment Heating (DCH)”, Short Course on Severe Accident Phenomenology, Pisa, Italy, January 10th–14th, 2011.

    Google Scholar 

  9. NEA/CSNI/R(2014)15 “OECD/SERENA Project Report—Summary and Conclusions”.

    Google Scholar 

  10. Piluso, P. (From Daniel MAGALLON SAP-2006 Lecture) “STEAM EXPLOSION”, Short Course on Severe Accident Phenomenology, Pisa, Italy, January 10th–14th, 2011.

    Google Scholar 

  11. Saas L., Le Tellier R., Bajard S., Habert B “In-vessel corium behavior: modelling of transients” International Symposium on Severe Accidents Simulation and Experiments for Nuclear Power Plants Sun Yat-sen University, Zhuhai, China, 2015.

    Google Scholar 

  12. Seiler J-.M., Fichot F., Cranga M., Azarian G., Atkhen K. «Etudes et stratégies pour la rétention du corium», RGN, 1 (2010) 63–72.

    Google Scholar 

  13. Zanchetti A., M. Hassanaly, A. Sanna, N. Méchitoua, H. Cordier, “Local hydrogen concentration evolution in a PWR nuclear containment in the event of a severe accident”, 24th International Conference on Nuclear Engineering, Chiba, Japan, paper ICONE23 –1542; 2015.

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Y. Laroche .

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

Atkhen, K., Dru, J., Laroche, Y. (2017). An Overview of Severe Accident Approach at EDF—Contribution of R&D Programs. 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_9

Download citation

  • DOI: https://doi.org/10.1007/978-981-10-2311-8_9

  • 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