Skip to main content

A homogenized multigroup diffusion theory for the neutron transport equation

  • Homogenization
  • Conference paper
  • First Online:
Computing Methods in Applied Sciences and Engineering, 1977, I

Part of the book series: Lecture Notes in Mathematics ((LNM,volume 704))

Abstract

We consider the steady multigroup neutron transport equation in a spatially periodic medium, with a spatially periodic source, and vacuum boundary conditions. We require (1) the ratio of a cell diameter to the diameter of the entire medium to be small, and (2) the transport operator to have N ≥ 1 eigenvalues which are small in magnitude, and simple. Then we show that the transport equation solution is approximated by the solution of an explicit system of N homogenized diffusion equations. We briefly discuss these equations and their properties.

Work performed under the auspices of the U. S. Energy Research and Development Administration.

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 34.99
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 46.00
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

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. P. Benoist, "Theorie du Coefficient de Diffusion dans un Reseau Comportant des Cavites," CEA-R-2278 Centre d'Etudes Nucleaires-Saclay (1964).

    Google Scholar 

  2. V. Deniz, "Study of the Kinetics of Thermalized Neutron Populations in Multiplying or Nonmultiplying Heterogeneous Media," Nucl. Sci. Eng. 28, 397 (1967).

    Google Scholar 

  3. E. M. Gelbard, "Anisotropic Neutron Diffusion in Lattices of Zero-Power Plutonium Reactor Experiments," Nucl. Sci. Eng. 54, 327 (1974).

    Google Scholar 

  4. E. W. Larsen, "Neutron Transport and Diffusion in Inhomogeneous Media. I," J. Math. Phys. 16, 1421 (1975).

    Article  MathSciNet  Google Scholar 

  5. E. W. Larsen, "Neutron Transport and Diffusion in Inhomogeneous Media, II," Nucl. Sci. Eng. 60, 357 (1976).

    Google Scholar 

  6. M. Williams, "Homogenization of Linear Transport Problems," Thesis Dissertation, New York University (1976).

    Google Scholar 

  7. A. Bensoussan, J. L. Lions, and G. C. Papanicolaou, "Boundary Layers and Homogenization of Transport Processes," lecture notes available from the Dept. of Mathematics, University of Utah, Salt Lake City, Utah (1976).

    MATH  Google Scholar 

  8. E. W. Larsen and M. Williams, "Neutron Drift in Heterogeneous Media," Nucl. Sci. Eng., to appear.

    Google Scholar 

  9. A. F. Henry, Nuclear Reactor Analysis, MIT Press, Cambridge, Mass. (1975).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Editor information

R. Glowinski J. L. Lions Iria Laboria

Rights and permissions

Reprints and permissions

Copyright information

© 1979 Springer-Verlag

About this paper

Cite this paper

Larsen, E.W. (1979). A homogenized multigroup diffusion theory for the neutron transport equation. In: Glowinski, R., Lions, J.L., Laboria, I. (eds) Computing Methods in Applied Sciences and Engineering, 1977, I. Lecture Notes in Mathematics, vol 704. Springer, Berlin, Heidelberg. https://doi.org/10.1007/BFb0063631

Download citation

  • DOI: https://doi.org/10.1007/BFb0063631

  • Published:

  • Publisher Name: Springer, Berlin, Heidelberg

  • Print ISBN: 978-3-540-09123-3

  • Online ISBN: 978-3-540-35411-6

  • eBook Packages: Springer Book Archive

Publish with us

Policies and ethics