Fusion Evaluated Nuclear Data Library - FENDL-3.2
(Nuclear data supersede all previous versions of FENDL-2.x and 3.x libraries)
Coordinators: Georg
Schnabel, and Roberto
Capote, and Andrej
Trkov LAST WEBPAGE UPDATE: Jan 10,
2022
FENDL-3.0 PRIMARY
REFERENCE:
R. Forrest, R. Capote, N. Otsuka, T. Kawano, A.J. Koning,
S. Kunieda, J-Ch. Sublet, and Y. Watanabe, INDC(NDS)-0628
(IAEA, Vienna, 2012).
(note: A new comprehensive documentation of the FENDL-3.2
library is in preparation).
The Fusion Evaluated Nuclear Data Library contains reaction data with a focus on the data requirements of fusion research facilities. Both operating and future facilities (e.g., ITER,DEMO, IFMIF) data needs are covered with current data extended up to 150 MeV. Development of FENDL libraries is described in the document links provided in the left column; links to previous FENDL releases are also listed.
The IRDFF-II library (International Reactor Dosimetry and Fusion File) released by the IAEA in January 2020 is recommended for neutron dosimetry in fusion facilities.
Library Contents: Transport
The FENDL-3.2 transport package contains evaluated nuclear data in ENDF-6 format as General Purpose files. Data are given for neutron-, proton- and deuteron-induced reactions up to a typical energy of 150 MeV. Data processing for transport applications has been undertaken (neutron data processing is similar to the processing of FENDL-3.0 library described in INDC(NDS)-0611 report). More details of the FENDL-3.2 data processing will be provided in the final FENDL-3.2 paper, which is in preparation. The following processed files for applications are given:
- FENDL/MC: Pointwise continuous-energy cross section data in ACE format for MCNP calculations; also includes probability tables (PT) in the unresolved resonance range.
- FENDL/MG: Contains multigroup cross section data in the
211n/42g Vitamin J+ energy structures (the 211n Vitamin J+
energy structure matches with the 175n Vitamin J energy
structure below 19.64 MeV) for multigroup transport codes in
two formats:
- FENDL/MG (MATXS), which includes files in MATXS format from the NJOY module MATXSR.
- FENDL/MG (GENDF), which contains data in GENDF format from the NJOY modules GROUPR and GAMINR.
- Data are available for 192 materials relevant for fusion at 293.6K. Additionally, the SIGACE package can be downloaded for Doppler broadening of ACE-formatted file - useful for generating ACE-formatted files at temperatures higher than 293.6K.
Notes on uncertainties: If covariance data are not available for a particular element of interest, covariance data of other libraries may be used (e.g., from TENDL-2019 library).
Changes since FENDL-3.1d:
- The neutron ENDF files of B-10, B11, O-18 and La-139 were updated by the Nuclear Data Section. Data from IRDFF-II, ENDF/B-VIII.0 and FENDL-3.1d were combined to match IRDFF-II dosimetry data.
- The neutron ENDF files of Cr-50, Cr-52, Cr-53, Cr-54, Fe-54, Fe-56, Fe-57, and O-16 were taken from the INDEN project.
- Yields in MF6/MT5 were corrected at 20 MeV in several neutron ENDF files by Chikara Konno and collaborators to resolve processing issues.
- Proton ENDF files for Li-6 and Li-7 have been taken from JENDL4/HE.
- Deuteron ENDF files for Li-6, Li-7, Be-9, C-12, C-13 have been taken from JENDL/DEU-2020.
- Photo-atomic ENDF files for Ne and Sm have been added.
Library Contents: Activation
Activation files from FENDL-3.0/A have been adopted. Note that selected activation channels
for neutron induced reactions which are included in the IRDFF-II library
may contain better quality evaluations than those listed in FENDL-3.0/A. However, IRDFF-II should not be used as a
comprehensive activation library as many activation reactions are not included in IRDFF-II not being neutron dosimetry reactions.
A similar situation arises for many proton and deuteron induced reactions evaluated for medical radionuclide production (e.g.,
see evaluated data for charged-particle induced monitor reactions,
for production of gamma-emitters for medical applications,
for production of positron-emitters for medical applications,
and for production of therapeutic radionuclides).
All those additional evaluations may contain better quality data but need to be incorporated channel-by-channel into the FENDL-3.0/A library.
That work is planned.
Download
The zipped files contain the entire library of a certain type.
Library | Sublibrary | ENDF | PENDF | ACE | MATXS | GENDF | GND |
---|---|---|---|---|---|---|---|
FENDL-3.2 (transport) | Neutron | [zip] | [zip] | [zip] | [zip] | ||
Photo-atomic | [zip] | [zip] | |||||
Proton | [zip] | [zip] | |||||
Deuteron | [zip] | [zip] | |||||
FENDL/A-3.0 (activation) | Neutron | [zip] | [zip] | [zip] | [zip] | [zip] | |
Proton | [zip] | [zip] | |||||
Deuteron (renorm) | [zip] | [zip] |