Skip to main content

Hydraulics and Thermo-hydraulics

  • Chapter
  • First Online:
Superphenix
  • 539 Accesses

Abstract

In nominal conditions, areas do coexist, with hot sodium (545 °C) and cold sodium (395 °C on primary and 345 °C on secondary sides), which will create thermo-hydraulics issues that have to be resolved in different locations of the reactor:

  • Fluctuation and thermal stripping risks, in the mixing zones with flows at different temperatures.

  • Complex zone between the core and the core cover plug and interaction with the inter sub-assembly flow.

  • Stratification in the pools and consequences on the structures and the inner vessel.

  • The intermediate heat exchanger and steam generator thermo-hydraulics.

  • Role of the cold pool as a mixer towards the flows coming from the eight intermediate heat exchangers.

  • Cold shocks or hot shocks during transient conditions.

In-gas thermo-hydraulics are complex too, with argon convective movements, generating thermal asymmetries and aerosol deposits. Furthermore, there are specific issues with the structures having thermal evolutions different between the part immersed in sodium and the part in gas. Finally, a section is devoted to the risks of gas entrainment, in particular passing through the reactor core.

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 149.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Hardcover Book
USD 199.99
Price excludes VAT (USA)
  • Durable hardcover 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. « Thermalhydraulic experience on the Phenix FBR », ICAPP 2015, J. Guidez.

    Google Scholar 

  2. Sodium thermal-hydraulics in the pool LMFBR primary vessel, Azarian, G. et al., Nuclear Engineering and Design 124 (1990).

    Google Scholar 

  3. Validation of fast reactor thermomechanical and thermohydraulic codes, IAEA, TECDOC-1318 (2002).

    Google Scholar 

  4. Some thermal hydraulic challenges in sodium cooled fast reactors, D. Tenchine Nuclear Engineering and Design 240(2010).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Joël Guidez .

Rights and permissions

Reprints and permissions

Copyright information

© 2017 Atlantis Press and the author(s)

About this chapter

Cite this chapter

Guidez, J., Prêle, G. (2017). Hydraulics and Thermo-hydraulics. In: Superphenix. Atlantis Press, Paris. https://doi.org/10.2991/978-94-6239-246-5_18

Download citation

  • DOI: https://doi.org/10.2991/978-94-6239-246-5_18

  • Published:

  • Publisher Name: Atlantis Press, Paris

  • Print ISBN: 978-94-6239-245-8

  • Online ISBN: 978-94-6239-246-5

  • eBook Packages: EnergyEnergy (R0)

Publish with us

Policies and ethics