Skip to main content

Heat release in the reactor core

  • Chapter
Multiphase Flow Dynamics 5
  • 2198 Accesses

Abstract

Chapter 1 contains introductory information about the heat release in the reactor core, the thermal power and thermal power density in the fuel, structures and moderator, the influence of the thermal power density on the coolant temperature, and the spatial distribution of the thermal power density. Finally, some measures are introduced for equalizing of the spatial distribution of the thermal power density.

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 219.00
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  • Alami, R., Ageron, P.: Evacuation et récupération de la chaleur des réacteurs nucleaires, Dunop, Paris (1958)

    Google Scholar 

  • Berger, H.-D.: Advances in reactor core fuel management. In: International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource”, Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14-19 (2008)

    Google Scholar 

  • Bonilla, C.F.: Nuclear engineering. McGraw-Hill, New York (1957)

    Google Scholar 

  • El-Wakil, M.M.: Nuclear Power Engineering. McGraw-Hill, New York (1962)

    Google Scholar 

  • Etherington, H.: Nuclear Engineering Handbook. McGraw-Hill, New York (1958)

    Google Scholar 

  • Grundlagen und Anwendung der Kerntechnik.: Bd III. Energie aus Kernprozessen. VDI-Verlag, Düsseldorf (1960)

    Google Scholar 

  • Henry, A.H.: Nuclear-reactor analysis, 8th edn. The MIT Press, Cambridge (1975) ISBN 0-262-08081-8

    Google Scholar 

  • Ivanov, K.: International activities of development and validation of coupled codes and their significance for realistic accident analyses. In: Annual Meeting on Nuclear Technology, Hamburg, May 27-29 (2008)

    Google Scholar 

  • Petrow, P.A.: Kernenergieanlagen. VEB Verlag Technik, Berlin (1959)

    Google Scholar 

  • Stacey, W.M.: Nuclear Reactor Physics. John Wiley & Sons, New York (2001); ISBN 0 471-39127-1

    Google Scholar 

  • Weinberg, A.M., Wigner, E.P.: The physical theory of neutron chain reactors. The University of Chicago Press, Chicago, (1959); Library of Congress Catalog 58-8507

    Google Scholar 

Download references

Authors

Rights and permissions

Reprints and permissions

Copyright information

© 2011 Springer-Verlag Berlin Heidelberg

About this chapter

Cite this chapter

Kolev, N.I. (2011). Heat release in the reactor core. In: Multiphase Flow Dynamics 5. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-20601-6_1

Download citation

  • DOI: https://doi.org/10.1007/978-3-642-20601-6_1

  • Publisher Name: Springer, Berlin, Heidelberg

  • Print ISBN: 978-3-642-20600-9

  • Online ISBN: 978-3-642-20601-6

  • eBook Packages: EngineeringEngineering (R0)

Publish with us

Policies and ethics