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RCPO1 - A Monte Carlo program for solving neutron and photon transport problems in three dimensional geometry with detailed energy description and depletion capability
Author(s) -
II Ondis L.A.,
L.J. Tyburski,
B.S. Moskowitz
Publication year - 2000
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/755403
Subject(s) - monte carlo method , neutron , nuclear physics , physics , photon , piping , range (aeronautics) , neutron transport , thermalisation , computational physics , nuclear engineering , materials science , atomic physics , optics , engineering , mathematics , statistics , composite material , thermodynamics
The RCP01 Monte Carlo program is used to analyze many geometries of interest in nuclear design and analysis of light water moderated reactors such as the core in its pressure vessel with complex piping arrangement, fuel storage arrays, shipping and container arrangements, and neutron detector configurations. Written in FORTRAN and in use on a variety of computers, it is capable of estimating steady state neutron or photon reaction rates and neutron multiplication factors. The energy range covered in neutron calculations is that relevant to the fission process and subsequent slowing-down and thermalization, i.e., 20 MeV to 0 eV. The same energy range is covered for photon calculations

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