![]() The library is in a psuedo ENDF-6 format - i.e. The library contains 20,049 excitation functions of reactions on stable and unstable targets for neutron energies up to 20 MeV. Russian activation data library released in 1993. The TENDL library is based on both default and adjusted TALYS calculations and is complemented by data from other sources whenever required, e.g. TENDL is a nuclear data library which provides in ENDF format the output of the TALYS nuclear model code system for direct use in both basic physics and applications. Significant contributions to the experimental database were made by participants of the WPEC Subgroup 7. The new evaluations of the cross-section standards also include covariance matrices of the uncertainties that contain fully justifiable values. The evaluations of the neutron cross-section standards were finalized in October 2005. The need to re-evaluate the cross-section standards at the beginning of the 21st century is based on the appearance of a significant amount of precise experimental data and developments in the methodology of analysis and evaluation. Not many cross-sections can be defined as absolute - most cross-sections are measured relative to the cross-section standards for normalization to absolute values. International Neutron cross-section standards are important in the measurement and evaluation of all other neutron reaction cross-sections. The library is in ENDF-6 format and contains data for 686 materials from 1-H-1 to 100-Fm-257. Russian File of Evaluated Neutron Data, released in 2010. The library is in ENDF-6 format and contains data for 406 materials from 1-H-1 to 100-Fm-255. Japanese Evaluated Neutron Data Library, released in 2010. The JEFF-3.2 general purpose library has been released on Maand contains incident neutron data for 472 nuclides or elements from 1-H-1 to 100-Fm-255. The Joint Evaluated Fission and Fusion File is an evaluated library produced via an international collaboration of Data Bank member countries co-ordinated by the JEFF Scientific Co-ordination Group, under the auspices of the NEA Data Bank. The reference to the ENDB/B-VII.1 library is Nuclear Data Sheets, Vol. The library is in ENDF-6 format and contains data for more than 400 materials from 1-H-1 to 100-Fm-255. NFY - Neutron-induced fission product yields.SFY - Spontaneous fission product yields.The library is divided into 14 sublibraries: The US evaluated nuclear data library released in December 2011. The library contains neutron-induced data up to 20 MeV for 240 materials from 1-H-1 to 98-Cf-249. The Chinese Evaluated Nuclear Data Library, released in December 2009. The library is in ENDF-6 format and contains data for 372 files for isotopes from hydrogen to curium and the incident neutron energies from the thermal one up to 20 MeV. Russian evaluated neutron data library, 2016. Download the complete library General Purpose Libraries ![]()
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