DLC-0211 ZZ-UTXS6 (Last modified 09-JUL-2002)

ZZ-UTXS6, MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures 
from 300 to 1365 K.


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



2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES 
AVAILABLE - 

Program-name         Package-ID  Status
ZZ-UTXS6             DLC-0211/01 Tested

Machines used:
Package-ID     Orig.Computer                       Test Computer
DLC-0211/01    UNIX gen. W.S.                      PC Pentium III 500



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: --



4. METHOD - 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.



5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -



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



7. UNUSUAL FEATURES -



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).



9. STATUS
DLC-0211/01: 09-JUL-2002 Tested at NEADB



10. REFERENCES  - 
- J. F. Briesmeister, Ed.
"MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709-M 
(April 2000).
DLC-0211/01:
- 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.



12. PROGRAMMING LANGUAGE -DLC-0211/01: 



13. SOFTWARE REQUIREMENTS -



14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -



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



16. MATERIAL AVAILABLE -DLC-0211/01:
211mnycp.txt  list of files
D211.pdf  documentation file
D211tar0.tar  UTXS library in compressed archive file
Readme.rsi  readme file



17. CATEGORIES  - 

- Z.  Data.



Keywords: CROSS SECTIONS, DATA LIBRARY, DOSIMETRY, FISSION PRODUCTS, 
MONTE CARLO METHOD, REACTION