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Accession Number DE2013-1016585
Title Overview of Monte Carlo Neutron Transport Codes.
Publication Date 2013
Media Count 10p
Personal Author B. L. Kirk
Abstract The Radiation Safety Information Computational Center (RSICC) is the designated central repository of the United States Department of Energy (DOE) for nuclear software in radiation transport, safety, and shielding. Since the center was established in the early 60's, there have been several Monte Carlo particle transport (MC) computer codes contributed by scientists from various countries. An overview of the neutron transport computer codes in the RSICC collection is presented.
Keywords Computer codes
Monte Carlo method
Neutron transport
Neutrons
Radiation protection
Radiation transport
Safety
Shielding
Transport


 
Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77F - Radiation Shielding, Protection, & Safety
46 - Physics
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1323
Contract Number DE-AC05-00OR22725

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