DocumentCode
839296
Title
Recent MCNP developments
Author
Hendricks, J.S. ; Briesmeister, J.F.
Author_Institution
Los Alamos Nat. Lab., NM, USA
Volume
39
Issue
4
fYear
1992
fDate
8/1/1992 12:00:00 AM
Firstpage
1035
Lastpage
1040
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;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/23.159755
Filename
159755
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