|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|DLC-0212/01||Many Computers||PC Pentium III 500|
The ENDF/B data library, released by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory, was updated to ENDF/B-VI, Release 7. These data were processed into the form of temperature dependent cross sections at LLNL and are being distributed as POINT2000. Many changes were made in ENDF/B-VI evaluation between the previous version of this library (POINT97), which was based on release 4 data, and the current version (POINT2000). See the included UCRL-ID-12776-Rev-1 document for details on these changes.
The original evaluated data include cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in applications, these ENDF/B-VI, Release 7 data were processed into the form of temperature dependent cross sections at eight temperatures between 0 and 2100 Kelvin, in steps of 300 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy. POINT2000 contains all of the evaluations in the ENDF/B-VI general purpose library, which contains evaluations for 324 materials (isotopes or naturally occurring elemental mixtures of isotopes). No special purpose ENDF/B-VI libraries, such as fission products, thermal scattering, photon interaction data are included. The majority of these evaluations are complete, in the sense that they include all cross sections over the energy range 10-5 eV to at least 20 MeV. However, the following are only partial evaluations that either only contain single reactions and no total cross section (Mg24, K41, Ti46, Ti47, Ti48, Ti50 and Ni59), or do not include energy dependent cross sections above the resonance region (Ar40, Mo92, Mo98, Mo100, In115, Sn120, Sn122 and Sn124).
The PREPRO2000 code system was used to process the ENDF/B data. Listed below are the steps, including the PREPRO2000 codes, which were used to process the data in the order in which the codes were run.
Linearly interpolable, tabulated cross sections (LINEAR)
Including the resonance contribution (RECENT)
Doppler broaden all cross sections to temperature (SIGMA1)
Check data, define redundant cross sections by summation (FIXUP).
|Package ID||Status date||Status|
D. E. Cullen, "PREPRO2000: The 2000 ENDF/B Pre-Processing Codes," Nuclear Data Section, IAEA, IAEA-NDS-39, Rev. 10 (April 1, 2000).
D. E. Cullen, "TART98: A Coupled Neutron-Photon 3-D, Time Dependent, Combinatorial Geometry Monte Carlo Transport Code," UCRL-ID-126455, Rev. 2 (November 1998.)
Keywords: ENDF/B, cross sections, evaluated data.