Descripción
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In July 2006 the NEA/Data Bank made available upon request the JEFF-3.1 library in ACE format (NEA-1768 ZZ-MCJEFF3.1NEA). This library contains continuous energy neutron cross section data files for use in the Monte Carlo program MCNP. The nuclides processed are all the evaluations of the General Purpose Library and Thermal Scattering JEFF-3.1 Library, including the important light nuclei, structural materials, fission products, control rod materials and burnable poisons, all major and minor actinides. | |
Internacional
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Nombre congreso
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International Conference on Nuclear Data for Science and Technology (ND2007) |
Tipo de participación
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960 |
Lugar del congreso
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Nize (France) |
Revisores
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Si |
ISBN o ISSN
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DOI
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Fecha inicio congreso
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22/04/2007 |
Fecha fin congreso
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27/04/2007 |
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Título de las actas
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