1. NAME AND TITLE OF DATA LIBRARY
POINT2000: A Temperature-Dependent, Linearly Interpolable, Tabulated Cross Section Library Based on ENDF/B-VI, Release 7.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
None included. Any codes which treat the ENDF/B-VI format can be used as data retrieval programs.
3. CONTRIBUTOR
Lawrence Livermore National Laboratory, Livermore, California.
4. HISTORICAL BACKGROUND AND INFORMATION
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 7. These data were processed into the form of temperature dependent cross sections at LLNL and are being distributed as POINT2000 by RSICC and the National Nuclear Data Center (NNDC). 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.
5. APPLICATION OF THE DATA
As distributed, 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 CCC-638/TART96 code package will soon be updated to TART2000, which is recommended for use with these data. Codes within TART2000 can be used to display these data or to run calculations using these data.
6. SOURCE AND SCOPE OF DATA
The PSR-351/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).
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
No data retrieval program is included in the package. The PSR-351/PREPRO2000 package may be used to plot the POINT2000 data. The PSR-333/CHENDF6.12 code system for handling ENDF/B data may be used to access these data.
8. DATA FORMAT AND COMPUTER
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. The entire library requires approximately 1.6 gigabyte of storage. (D00212/MNYCP/00).
9. TYPICAL RUNNING TIME
Not applicable.
10. REFERENCES
a. Documentation available with library:
D. E. Cullen, "A Temperature Dependent ENDF/B-VI, Release 7, Cross Section Library," UCRL-ID-12776-Rev-1 (November 22, 2000).
b. Other useful documentation:
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.)
11. CONTENTS OF LIBRARY
The data are approximately 1.6 gigabyte in size and are distributed on two CD's written in DOS format. The referenced document in 10.a is also included on CD.
12. DATE OF ABSTRACT
June 2000.
KEYWORDS: BASED ON ENDF/B-VI; EVALUATED NEUTRON CROSS SECTIONS.