|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|DLC-0192/01||Many Computers||PC Pentium III 500|
NUMBER OF GROUPS:--
MATERIALS: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd.
TEMPERATURES: Between 0 and 2100 K, in steps of 300.
ORIGIN: ENDF/B-6, Release 4
As distributed, the original evaluated data includes 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 4 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. The library contains data for 321 evaluations.
The ENDF/B data library, available from the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory, was recently updated to ENDF/B-VI, Release 4. These data were processed into the form of temperature dependent cross sections at LLNL and are being distributed as POINT97 by RSICC.
The PREPRO97 code system was used to process the ENDF/B data.
Listed below are the steps, including the PREPRO97 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)
Note that the reference ENDF/B data are available from NNDC and are not included on the CD-ROM.
|Package ID||Status date||Status|
Keywords: ENDF/B, cross sections, evaluated data.