RSICC DATA LIBRARY DLC-219
1. NAME AND TITLE OF DATA LIBRARY
POINT2004: Temperature-Dependent, Linearly Interpolable, Tabulated Cross Section Library Based on ENDF/B-VI, Release 8.
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
ENDF/B-VI, Release 8, available from the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory, were processed into the form of temperature dependent cross sections at LLNL and are being distributed as POINT2004 by RSICC, the National Nuclear Data Center (NNDC) and the Nuclear Data Centre at the International Atomic Energy Agency .
Both the current Point 2004 and the previously published Point 2003 are based on exactly the same ENDF/B-VI, Release 8 data. The difference between them is the accuracy to which the reconstructed data is presented and the media on which they are distributed. When Point 2003 was released, constraints on the size of the data files to conveniently fit onto CDs required construction of the cross section to a looser tolerance than that recommended for many applications. Even with this limitation, Point 2003 contained about 1.8 Gigabytes of data and was distributed on three CDs.
Point 2004 is distributed on a single DVD, rather than a series of CDs. The additional space allowed tightening of the tolerance on the data to reconstruct cross sections at all energies and temperatures to 0.1 % accuracy, which is what the author routinely use in his applications. The result is a single DVD containing 4.3 Gigabyte of data.
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 this library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 and 2100 Kelvin, in steps of 300 Kelvin. It has also been processed to five astrophysics like temperatures, 1, 10, 100 eV, 1 and 10 keV. For reference purposes, 300 Kelvin is approximately 1/40 eV, so that 1 eV is approximately 12,000 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy.
POINT2004 contains all of the evaluations in the ENDF/B-VI general purpose library, which contains evaluations for 328 materials (isotopes or naturally occurring elemental mixtures of isotopes). No special purpose ENDF/B-VI libraries, such as fission products, thermal scattering, or 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 contain only 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/TART20002 code package is recommended for use with these data. Codes within TART can be used to display these data or to run calculations using these data.
6. SOURCE AND SCOPE OF DATA
The PSR-351/PREPRO2002 code system was used to process the ENDF/B data. Listed below are the steps, including the PREPRO2002 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)
5) Update evaluation dictionary in MF/MT=1/451 (DICTIN)
For the "cold" (0 Kelvin) data steps 1), 2) and 4), 5) were used. For the data at other temperatures, after steps 1) and 2), the data was Doppler broadened to each temperature using step 3), and the results were then made consistent with the ENDF/B formats and conventions using steps 4) and 5), to produce the final distributed data. The result is linearly interpolable in energy, tabulated, temperature dependent cross sections in the ENDF/B-VI format, ready to be used in applications.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
No data retrieval program is included in the package. The PSR-351/PREPRO2002 or PREPRO2004 package may be used to plot the POINT2004 data. The PSR-333/CHENDF6.13 or newer 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 4 gigabyte of storage. (D00219/MNYCP/00).
9. TYPICAL RUNNING TIME
Not applicable.
10. REFERENCES
a. Documentation available with library:
D. E. Cullen, “POINT 2004, A Temperature Dependent ENDF/B-VI, Release 8, Cross Section Library,” UCRL-TR-202284 (April 1, 2004).
b. Other useful documentation:
D.E. Cullen, "PREPRO 2002: 2002 ENDF/B Pre‑processing Codes," IAEA‑NDS‑39, Rev. 11 (February 5, 2003).
D. E. Cullen, "TART2002 ‑ A Coupled Neutron‑Photon 3‑D, Combinatorial Geometry, Time Dependent Monte Carlo Transport Code," UCRL‑ID 126455, Rev. 3 (November 2000).
11. CONTENTS OF LIBRARY
The library is approximately 4.3 gigabyte in size and is distributed on a single DVD.
12. DATE OF ABSTRACT
February 2005.
KEYWORDS: BASED ON ENDF/B-VI; EVALUATED NEUTRON CROSS SECTIONS.