Approximate Methods in Reactor Shielding Calculations

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


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.


Diffusion Equation Elastic Scattering Total Flux Reactor Core Diffusion Theory 
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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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