FENDL-3.1:
Fusion Evaluated Nuclear Data Library Ver.3.1
WARNING
The FENDL-3.1 library is superseded by an updated version
Participants of the Technical Meeting in October/November 2007 (INDC(NDS)-0525) defined the objective of the CRP, which was to update and extend the FENDL-2.1 library to make it applicable to both fusion devices such as ITER and DEMO and to material test facilities such as IFMIF. The extension required the addition of several materials, an extension of the energy range to higher energies and the addition of data for charged particle-induced reactions. Special attention was needed to ensure realistic covariance data that would make the library suitable for all fusion technology studies. The reports of the three RCMs are available (INDC(NDS)-0547, INDC(NDS)-0567 and INDC(NDS)-0602) as well as the summary documentation of the FENDL-3.0 library (INDC(NDS)-0628). A summary of the contributions by participants in the CRP is given in INDC(NDS)-0645.
New in Version FENDL-3.1
Several problems were reported by Chikara Konno from JAEA in his slides and a summary document regarding the KERMA and DPA data in the processed FENDL-3.0 libraries in ACE and MATXS format. To conform with the decision of the FENDL project participants, the choice of the source data files was not changed, except for a trivial correction to the Q-value in the N-15 evaluation. To address processing problems, patches for NJOY2012 were prepared and the library assembly process was repeated. As recommended by Konno, the upper kinematic limit for heating was applied in all cases. Further details can be found in the summary report by D.L. Aldama. The Neutron (shadow) library, the Proton, the Deuteron and the FENDL/A-3.0 data were not changed.
Download
| Library | Sublibrary | ENDF | PENDF | ACE | MATXS | GENDF | GND |
|---|---|---|---|---|---|---|---|
| FENDL-3.1 | Neutron | [zip] | [zip] | [zip] | [zip] | ||
| Photo-atomic | [zip] | [zip] | |||||
| Neutron (shadow) | [zip] | [zip] | |||||
| Proton | [zip] | [zip] | |||||
| Deuteron | [zip] | [zip] | |||||
| FENDL/A-3.0 | Neutron | [zip] | [zip] | [zip] | [zip] | [zip] | |
| Proton | [zip] | [zip] | |||||
| Deuteron | [zip] | [zip] | |||||
| Deuteron (renorm) | [zip] | [zip] |
Contents
The FENDL-3.1 package contains evaluated nuclear data in ENDF-6 format both as General Purpose and Activation Files. In each case data are given for neutron-, proton- and deuteron-induced reactions up to a typical energy of 150 MeV for General Purpose and 60 MeV for Activation files. Not all targets in the General Purpose library contain covariance data and so an extract of the TENDL-2011 library with all the 180 targets of FENDL-3.1 is provided as a "shadow library" so that complete uncertainty calculations can be done. Processing of the basic files has been done so that a series of files are available for applications (INDC(NDS)-0611).
- FENDL/MC-3.1: Pointwise continuous-energy cross section data in ACE format for MCNP calculations; also includes probability tables (PT) in the unresolved resonance range.
- FENDL/MG-3.1: 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-3.1 (MATXS), which includes files in MATXS format from the NJOY module MATXSR.
- FENDL/MG-3.1 (GENDF), which contains data in GENDF format from the NJOY modules GROUPR and GAMINR.
- Data are available for 180 materials relevant for fusion at 300K. Additionally, the SIGACE package can be downloaded for Doppler broadening of ACE-formatted file - useful for generating ACE-formatted files at temperatures higher than 300K.
- For the sake of completeness, NJOY inputs to generate ACE, MATXS and GENDF files are supplied. Furthermore, NJOY-99.90 local updates, as well as the auxiliary programs and WINDOWS batch files used to update and verify the FENDL-3.1 transport sublibraries, are also available.
- FENDL/A-3.0 is available in PENDF and GENDF formats. In addition the neutron-induced file is also available in a Generalised Nuclear Data (GND) format.
Verification and Validation
To verify the processing of the FENDL-3.1 library into ACE format the QA procedure as described in the (INDC(SEC)-0107) document was applied. It consists of converting the ACE cross sections back into ENDF format and comparing with the pointwise cross sections prepared with the PREPRO package. The procedure does not test all features of the ACE file, but is useful for trapping severe processing errors. A similar procedure has been (partially) implemented to verify the files in the MATXS format, but this is still work in progress.
The complete validation of the various parts of FENDL-3.1 is expected to be carried out following its release. However, the validation of preliminary files is reported in the presentations at the various RCMs and also for the activation file as reports (INDC(NED)-011, INDC(NED)-012, and INDC(UK)-0094).