Title :
Recent MCNP developments
Author :
Hendricks, J.S. ; Briesmeister, J.F.
Author_Institution :
Los Alamos Nat. Lab., NM, USA
fDate :
8/1/1992 12:00:00 AM
Abstract :
MCNP is a general purpose Monte Carlo code for calculating the time-dependent-continuous-energy transport of neutrons, photons, and/or electrons in three-dimensional geometries. The authors focus on a number of recent significant advances and new directions for MCNP, the MCNP benchmark project that also provides insight into the reliability of modern computer codes and data libraries, and a timing study measuring the performance of MCNP on several computing platforms
Keywords :
Monte Carlo methods; neutron transport theory; photon transport theory; physics computing; transport processes; electrons; general purpose Monte Carlo code; neutrons; photons; time-dependent-continuous-energy transport; timing study; Aerospace safety; Electrons; Fusion reactor design; Geometry; Laboratories; Monte Carlo methods; Neutrons; Physics computing; Well logging; Workstations;
Journal_Title :
Nuclear Science, IEEE Transactions on
