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- Evaluated Nuclear Data File (ENDF)
ENDF B-VIII 0 fully incorporates the new Neutron Data Standards, includes improved thermal neutron scattering data and uses new evaluated data from the Coordinated International Evaluation Library Organization (CIELO) pilot project for neutron reactions on 1 H, 16 O, 56 Fe, 235 U, 238 U and 239 Pu
- ENDF B-VIII. 0 Evaluated Nuclear Data Library
The U S 's Evaluated Nuclear Data File (ENDF) is the default low energy nuclear data library in particle transport codes such as MCNP, SCALE and even GEANT4
- ENDF Releases - nndc. bnl. gov
The ENDF B-VIII 1 release is the newest evaluated nuclear data library produced, distributed, and recommended by CSEWG for use in nuclear science and technology applications
- ENDF Library - nndc. bnl. gov
The NNDC is responsible for assigning ENDF reference numbers for all formal laboratory reports associated with the ENDF system
- Download ENDF B-VIII. 0 - Brookhaven National Laboratory
Download ENDF B-VIII 0 Full ENDF B-VIII 0 Library [488 Mb Zip file] [Format Manual] Download checksums:
- ENDF B-VII. 1 Evaluated Nuclear Data Library
It contains thermal scattering-law data, largely supplied by LANL, with the addition of SiO 2 in ENDF B-VII 1 from ORNL The neutron cross section standards sublibrary was carried over from ENDF B-VII 0 unchanged
- ENDF-6 Formats Manual
The ENDF system was developed for the storage and retrieval of evaluated nuclear data to be used for applications of nuclear technology These applications control many features of the system including the choice of materials to be included, the data used, the formats used, and the testing required before a library is released
- ENDF B-V Evaluated Nuclear Data Library
Twenty-four materials and reactions are available in ENDF-V format containing covariance files The Department of Energy put restrictions on the distribution of the library for the first time
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