Computer Programs
DLC-0192 ZZ-POINT97.
last modified: 02-JUL-2002 | catalog | categories | new | search |

DLC-0192 ZZ-POINT97.

ZZ POINT97, Temperature-Dependent ENDF/B-6 Cross-Sections at 8 Temperature Between 0K and 2100K

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1. NAME OR DESIGNATION OF PROGRAM

ZZ-POINT97.

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2. COMPUTERS

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Program name Package id Status Status date
ZZ-POINT97 DLC-0192/01 Tested 02-JUL-2002

Machines used:

Package ID Orig. computer Test computer
DLC-0192/01 Many Computers PC Pentium III 500
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3. DESCRIPTION OF PROGRAM OR FUNCTION

FORMAT: ENDF/B-6

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
WEIGHTING SPECTRUM:--

 

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.

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4. METHODS

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.

  1. Linearly interpolable, tabulated cross sections (LINEAR)

  2. Including the resonance contribution (RECENT)

  3. Doppler broaden all cross sections to temperature (SIGMA1)

  4. 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.

 

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9. STATUS
Package ID Status date Status
DLC-0192/01 02-JUL-2002 Screened
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10. REFERENCES
  • D.E. Cullen: The 1996 ENDF/B Pre-Processing Codes IAEA-NDS-39, Rev.9 (November 1996)

DLC-0192/01, included references:
- D.E. Cullen:
A Temperature Dependent ENDF/B-VI, Release 4, Cross Section Library
UCRL-ID-127776 (July 4, 1997)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

 

Developed by:   Lawrence Livermore National Laboratory
                Livermore, California, U.S.A.

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16. MATERIAL AVAILABLE
DLC-0192/01
K0 0 Kelvin cross sections
K300 300 Kelvin cross sections
K600 600 Kelvin cross sections
K900 900 Kelvin cross sections
K1200 1200 Kelvin cross sections
K1500 1500 Kelvin cross sections
K1800 1800 Kelvin cross sections
K2100 2100 Kelvin cross sections
UCRL-ID-127776 (July 4, 1997)
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17. CATEGORIES
  • ZZZ. ARCHIVE

Keywords: ENDF/B, cross sections, evaluated data.