The ENDL92 Neutron Data Library

Released: 1995-07-25

The ENDL92 library contains 106 data files based on evaluations from Lawrance Livermore National Laboratory (LLNL), including 100 data files from the original library, four specially modified data files for Zn, Sn, Pt, and Hg from X Division, and two data files for average fission products. The Data Team did not process these evaluations as we did for the previous ENDL85 data library. Instead we obtained MCNP compatible data files from LLNL and performed a modified QA process on them. Some changes have been made to a number of the original files from LLNL to make them compatible with MCNP. The data files for this library have been given the ZAID designator of .42c.

The ENDL92 library has data for four nuclides previously unavailable to MCNP®: Ne-20, Zn, Sb, and Hg. The incident neutron energy range of the data files extends from E=0.0 eV to 30.0 MeV, with the exception of Am-242 which only extends to 20 MeV. This library is valuable in that it will allow the user to make comparisons between ENDL and ENDF evaluations and libraries. However, we recommend the use of this library for the generation of final results only in the absence of other available libraries for specific nuclides.

The report "Summary Documentation for the ENDL92 Continuous-Energy Neutron Data Library (Release 1)" LA-UR-96-327 describes the general characteristics of the library and the QA process that was followed in the absence of having the original evaluations available to us (the Evaluated Nuclear Data Library (ENDL) from LLNL).

Benchmarking

The ENDL92 Library has been used in some benchmarking activities:

1. Spectral Measurements in Critical Assemblies: MCNP Specifications and Calculated Results", LA-13675 (Document and Appendices)
2. Criticality Results for ENDF/B-V, ENDF/B-VI and ENDL92, excerpt from presentation LA-UR-99-5598

Documentation

3. "Spectral Measurements in Critical Assemblies: MCNP Specifications and Calculated Results," Frankle, S.C, Briesmeister, J.F, (1999) LA-13675 (Appendices)

4. "Summary Documentation for the ENDL92 Continuous-Energy Neutron Data Library (Release 1)," Frankle, S.C, (2002), LA-UR-96-327(Improved Figures)

5. "Supplement to the Summary Documentation for the ENDL92 Continuous-Energy Neutron Data Library (Release 1)," Frankle, S.C, (1996), LA-UR-96-327

6. "k eff , Reaction Rates and Spectral Measurements in Critical Assemblies," Frankle, S.C, (1999), LA-UR-99-5598