Nuclear data for MCNP
Nuclear data for MCNP
The sources of neutron and photon transport data are described as well as the processing of the evaluated data sets into continuous-energy and multigroup cross-section sets. The procedures for checking and validating the processed data are discussed. The question of why so many data sets are available is addressed by indicating the differences between data sets as well as their relative strengths and weaknesses. Suggestions are made to help the MCNP user in selecting appropriate cross-section sets.
- University of North Texas United States
- Los Alamos National Laboratory United States
Nucleon Reactions, Fission, Neutral-Particle Transport, Neutron Reactions, Photonuclear Reactions, Libraries, 73 Nuclear Physics And Radiation Physics, Photon Transport, Hadrons, Multigroup Theory, Hadron Reactions, Neutron Transport Theory, Transport Theory 654003* -- Radiation & Shielding Physics-- Neutron Interactions With Matter, Radiation Transport, Baryons, Neutron Transport, Nuclear Reactions, Fission Neutrons, Fermions, Nucleons, Prompt Neutrons, Neutrons, Nuclear Data Collections, Multiplicity, Cross Sections, Baryon Reactions, Monte Carlo Method, Elementary Particles
Nucleon Reactions, Fission, Neutral-Particle Transport, Neutron Reactions, Photonuclear Reactions, Libraries, 73 Nuclear Physics And Radiation Physics, Photon Transport, Hadrons, Multigroup Theory, Hadron Reactions, Neutron Transport Theory, Transport Theory 654003* -- Radiation & Shielding Physics-- Neutron Interactions With Matter, Radiation Transport, Baryons, Neutron Transport, Nuclear Reactions, Fission Neutrons, Fermions, Nucleons, Prompt Neutrons, Neutrons, Nuclear Data Collections, Multiplicity, Cross Sections, Baryon Reactions, Monte Carlo Method, Elementary Particles
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