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Energy Effects in Modeling Neutron Diffusion: Two-Group Models

  • Bahman Zohuri
Chapter

Abstract

In this chapter, we derive the multi-group diffusion equation (MGDE) and we illustrate how do we solve them in a way that allows us to calculate an accurate eigenvalue and accurate reaction rates. Since the cross sections vary wildly by multiple orders of magnitude over the energy range in a typical nuclear reactor, the major problem becomes one of determining accurate multi-group cross sections for the design problem under consideration.

References

  1. 1.
    J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis (Wiley). 1976 editionGoogle Scholar
  2. 2.
    P.F. Zweifel, Reactor Physics (McGraw-Hill, New York, 1973)CrossRefGoogle Scholar

Copyright information

© Springer Nature Switzerland AG 2019

Authors and Affiliations

  • Bahman Zohuri
    • 1
  1. 1.Galaxy Advanced Engineering, Inc.University of New MexicoAlbuquerqueUSA

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