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Carter, L.L.; Hendricks, J.S.
Hanford Engineering Development Lab., Richland, WA (USA)1979
Hanford Engineering Development Lab., Richland, WA (USA)1979
AbstractAbstract
[en] A benchmark for calculation of neutron transport through iron is now available based upon a rigorous Monte Carlo treatment of ENDF/B-IV and ENDF/B-V cross sections. The currents, flux, and dose (from monoenergetic 2, 14, and 40 MeV sources) have been tabulated at various distances through the slab using a standard energy group structure. This tabulation is available in a Los Alamos Scientific Laboratory report. The benchmark is simple to model and should be useful for verifying the adequacy of one-dimensional transport codes and multigroup libraries for iron. This benchmark also provides useful insights regarding neutron penetration through iron and displays differences in fluxes calculated with ENDF/B-IV and ENDF/B-V data bases
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Oct 1979; 19 p; American Nuclear Society meeting; San Francisco, CA, USA; 12 - 16 Nov 1979; CONF-791103--49; Available from NTIS., PC A02/MF A01
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Report
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Conference
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