Criticality benchmark results for the ENDF60 library with MCNP{trademark}

Criticality benchmark results for the ENDF60 library with MCNP{trademark} [electronic resource]

The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation transport code MCNP4A, was released in the fall of 1994. The ENDF60 library is comprised of 124 nuclide data files based on the ENDF/B-VI (B-VI) evaluations through Release 2. Fifty-two percent of th...

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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, 1995.
Subjects:
Criticality.
Benchmarks.
M Codes.
Monte Carlo Method.
Nuclear Data Collections.
Neutron Transport.
Nuclear Reactor Technology ;66 Physics.

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Call Number: E 1.99:CONF-951006--20
E 1.99:CONF-951006--20 Available

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