The CENDL-3.1 neutron-induced cross section data in the 709 group structure ENDF-6 format files are available directly from:
http://www.ccfe.ac.uk/easy-data/FISPACT ... 15data.tgz
The compressed file is approximately 6.7 Gb in size. The uncompressed data is over 30 Gb in size. Please note that this includes a substantial amount of data:
- Neutron-induced data
----> 709 group cross sections for 294K, 600K, 900K, kT=5keV and kT=30keV
----> Probability tables for 709 group cross sections at 294K, 600K and 900K
----> Neutron-induced fission yields from GEFY-5.2
----> PKA spectra for all neutron-induced reactions
- Proton, gamma, alpha and deuteron-induced data
----> 162 group cross sections
----> UKFY-4.1 charged particle fission yields
- GEFY-5.2 spontaneous fission yields
It is recommended that users install the uncompressed files within their FISPACT-II installation directory under ENDFdata.
TENDL-2015 nuclear data available
- Michael Fleming
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TENDL-2015 nuclear data available
Michael Fleming, PhD
D3/1.56 Culham Science Centre
UK Atomic Energy Authority
Abingdon, OX14 3DB
+44 (0) 1235 466884
michael.fleming@ukaea.uk
D3/1.56 Culham Science Centre
UK Atomic Energy Authority
Abingdon, OX14 3DB
+44 (0) 1235 466884
michael.fleming@ukaea.uk
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