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Approximate Methods in Reactor Shielding Calculations

  • Carlo Ponti
Part of the Ettore Majorana International Science Series book series (EMISS, volume 3)

Abstract

The solution of any shielding problem requires the knowledge of the radiation flux and of its space-energy distribution. The determination of this flux by means of transport theory — in one of its more or less rigorous forms — is therefore always a necessary step. The methods of calculation that have been more widely applied for solving reactor shielding problems, are not the same as those applied for neutronic calculations inside the reactor core.

Keywords

Diffusion Equation Elastic Scattering Total Flux Reactor Core Diffusion Theory 
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

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Copyright information

© Plenum Press, New York 1980

Authors and Affiliations

  • Carlo Ponti
    • 1
  1. 1.Joint Research CentreIspra (Varese)Italy

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