DLC-0211 ZZ-UTXS6.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-UTXS6.

3. DESCRIPTION OF PROGRAM OR FUNCTION

UTXS is a continuous-energy cross section libraries in ACE format suitable for the MCNP code were generated using the NJOY94.105 processing code. Libraries for various materials were generated at typical operating temperatures of Pressurized Water Reactor (PWR), Boiling Water Reactor (BWR), and the Russian PWR (VVER) as well as libraries for other non-reactor applications such as nuclear medicine.

FORMAT: ACE
NUMBER OF GROUPS: Continuous energy
NUCLIDES (107): H1, H2, H3, He3, He4, Li6, Li7, Be9, B10, B11, C-nat., N14, O16, Na23, Al27, Fe54, Fe56, Fe57, Fe58, Co59, Ni58, Ni60, Ni61, Ni62, Ni64, Cu63, Cu65, Zn-nat., Ga-nat., Ge72, Ge73, Ge74, Ge76, Zr90, Zr91, Zr92, Zr93, Zr94, Zr95, Zr96, Rh103, Rh105, Ag107, Ag109, Cd-nat., Cd106, Cd108, Cd110, Cd111, Cd112, Cd113, Cd114, Cd116, In-nat., In113, I127, I129, I130, I131, I135, Xe124, Xe126, Xe128, Xe129, Xe130, Xe131, Xe132, Xe133, Xe134, Xe135, Xe136, Cs133, Cs134, Cs135, Cs136, Cs137, Ba134, Ba135, Ba136, Ba137, Ba138, Ba140, Gd152, Gd154, Gd155, Gd156, Gd157, Gd158, Gd160, Er166, Er167, Hf-nat, Hf174, Hf176, Hf177, Hf178, Hf179, Au197, Pb206, Pb207, Pb208, Th230, Th232, U233, U234, U235, U236, U237, U238, Pu236, Pu237, Pu238, Pu239, Pu240, Pu241, Pu242, Pu243, Pu244, Am242, Am243

TEMPERATURES: 300 K, 450K, 479K, 500 K, 558K, 560 K, 570K, 579K, 600K, 620K, 755K, 833K, 900K, 920K, 1027K, 1100 K, 1145K, 1154K, and 1365K.

ORIGIN: ENDF/B-VI, BROND-2, CENDL-2
WEIGHTING SPECTRUM:

April 2005: This is the DVD version.

4. METHODS

The need for cross section libraries for various materials at different temperatures arose during the benchmark activities related to mixed oxide fuel (MOX) utilization in existing light water reactors. The current version, UTXS6, is based on ENDF/B-VI except for Zinc and Erbium for which the Russian (BROND-2) and the Chinese (CENDL-2) libraries were used.

The UTXS6 library went through preliminary testing and validation. The validation process consisted of three steps: checking the library structure, plotting comparison with standard cross sections from Los Alamos National Laboratory, and benchmarking against ENDF60 and experimental data.

The UTXS6 library was benchmarked against ENDF60 and experimental data for some nuclides. Experiments from the "International Handbook of Evaluated Criticality Safety Benchmark Experiments" (NEA/NSC/DOC(95) 1997) were used along with MCNP input files supplied with the electronic copy. Benchmark calculations were done with MCNP4B on SUN workstation.

6. TYPICAL RUNNING TIME

The ASCII-to-binary conversion can generally be accomplished within a few seconds, even for the large data files.

8. RELATED OR AUXILIARY PROGRAMS

MAKSF, which is distributed with CCC-700/MCNP4C, can be used to convert MCNP Type 1 data to Type 2 (binary).

10. REFERENCES

- J. F. Briesmeister, Ed.
"MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709-M (April 2000).

- M. S. Abdelrahman and N. M. Abdurrahman:
Cross Section Libraries for Studies of Plutonium Disposition in Light Water
Reactors
ANRCP-1999-28 (October 1999)

11. HARDWARE REQUIREMENTS

ASCII card images; Unix workstation.

The UTXS library distribution was prepared on a Unix system. On a Windows-based PC, one may use utilities such as WinZip(R) to unzip and extract the library files.

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:   The University of Texas
                Austin, Texas, USA

211mnycp.txt  list of files
D211.pdf  documentation file
D211tar0.tar  UTXS library in compressed archive file
Readme.rsi  readme file