MCNP{trademark} ENDF/B-VI iron benchmark calculations

MCNP{trademark} ENDF/B-VI iron benchmark calculations [electronic resource]

Four iron shielding benchmarks have been calculated for, we believe the first time, with MCNP4A and its new ENDF/B-VI library. These calculations are part of the Hiroshima/Nagasaki dose re-evaluation for the National Academy of Sciences and the Defense Nuclear Agency. We believe these calculations a...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Los Alamos National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1994.
Subjects:
M Codes.
Transport Theory.
Radiation Transport.
Monte Carlo Method.
Photon Transport.
Nuclear Data Collections.
Neutron Transport.
Shielding Materials.
Iron.
Nuclear Physics And Radiation Physics.

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Call Number: E 1.99: conf-941102--14
E 1.99: conf-941102--14 Available

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