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A Nodal Method for Transient Analysis of Multigroup Neutron Diffusion

  • Feyzi Inanc
Conference paper

Abstract

The purpose of the nodal model developed is to analyze the fast transient behavior of the reactor cores on the basis of time dependent multigroup neutron diffusion equation and precursor density equations given below. Although the current form of the model, which analyzes the transient behavior in one dimension without introducing the affects of the any feedback mechanisms such as temperature and Doppler affects, it is useful for gaining experience for further development of the model.

Keywords

Diffusion Equation Neutron Flux Legendre Polynomial Transient Behavior Adjacent Node 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    A. F. Rohach, Ann. Nucl. Energy., Vol. 13, No. 2, (1986)Google Scholar
  2. 2.
    A. F. Rohach, Ann. Nucl. Energy., Vol. 13, No. 10,(1986)Google Scholar
  3. 3.
    W. R. Cadwell, A. F. Henry and A. J. Vigilotti, WAPD-TM-416 (1964)Google Scholar

Copyright information

© Springer-Verlag Berlin Heidelberg 1988

Authors and Affiliations

  • Feyzi Inanc
    • 1
  1. 1.Nuclear Engineering DepartmentIowa State UniversityAmesUSA

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