Computer Programs
DLC-0212 ZZ-POINT2000.
last modified: 02-JUL-2002 | catalog | categories | new | search |

DLC-0212 ZZ-POINT2000.

ZZ POINT2000, Linearly Interpolable ENDF/B-VI.7 Data for 8 Temperatures

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1. NAME OR DESIGNATION OF PROGRAM

ZZ-POINT2000.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name Package id Status Status date
ZZ-POINT2000 DLC-0212/01 Tested 02-JUL-2002
ZZ-POINT2000 DLC-0212/02 Tested 02-JUL-2002

Machines used:

Package ID Orig. computer Test computer
DLC-0212/01 Many Computers PC Pentium III 500
DLC-0212/02 Many Computers PC Windows
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3. DESCRIPTION

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).

DLC-0212/02
April 2005: This is the DVD version.
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4. METHODS

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.

 

  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).

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8. RELATED OR AUXILIARY PROGRAMS

No data retrieval program is included in the package. The PREPRO2000 package may be used to plot the POINT2000 data.

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9. STATUS
Package ID Status date Status
DLC-0212/01 02-JUL-2002 Screened
DLC-0212/02 02-JUL-2002 Screened
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10. REFERENCES
  • 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.)

DLC-0212/01, included references:
- D.E. Cullen:
A Temperature Dependent ENDF/B-VI, Release 7, Cross Section Library
UCRL-ID-127776-Rev-1  (November 22, 2000)
DLC-0212/02, included references:
- D.E. Cullen:
A Temperature Dependent ENDF/B-VI, Release 7, Cross Section Library
UCRL-ID-127776-Rev-1  (November 22, 2000)
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11. HARDWARE REQUIREMENTS

In this library each evaluation is stored as a separate file. The entire library is in the computer independent ENDF/B-VI character format, which allows the data to be easily transported between computers.

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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-0212/01
K0 dir.      0 Kelvin cross sections
K300 dir.   300 Kelvin cross sections
K600 dir.   600 Kelvin cross sections
K900 dir.   900 Kelvin cross sections
K1200 dir.   1200 Kelvin cross sections
K1500 dir.   1500 Kelvin cross sections
K1800 dir.   1800 Kelvin cross sections
K2100 dir.   2100 Kelvin cross sections
D212.PDF   UCRL-ID-127776-Rev-1 Documentation in pdf format
P_label.exe  Optional labels for CD's
Point2k.doc Documentation in Word format
Point2k.pdf Documentation in pdf format

DLC-0212/02
K0 dir.      0 Kelvin cross sections
K300 dir.   300 Kelvin cross sections
K600 dir.   600 Kelvin cross sections
K900 dir.   900 Kelvin cross sections
K1200 dir.   1200 Kelvin cross sections
K1500 dir.   1500 Kelvin cross sections
K1800 dir.   1800 Kelvin cross sections
K2100 dir.   2100 Kelvin cross sections
D212.PDF   UCRL-ID-127776-Rev-1 Documentation in pdf format
P_label.exe  Optional labels for CD's
Point2k.doc Documentation in Word format
Point2k.pdf Documentation in pdf format
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17. CATEGORIES
  • ZZZ. ARCHIVE

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