RSICC DATA PACKAGE DLC-216

1. NAME AND TITLE OF DATA LIBRARY

MCB63NEA.BOLIB: ENDF/B-VI Release 3 Cross Section Library for Use with the MCNP Monte Carlo Code.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

MAKXSF: Preparer of Cross Sections from LANL MCNP package -distributed with MCNP.

3. CONTRIBUTORS

ENEA - Centro Ricerche, Bologna, Italy, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Molineaux, France.

4. HISTORICAL BACKGROUND AND INFORMATION

MCB63NEA.BOLIB is a pointwise library for nuclear fission applications produced at the Nuclear Data Centre of ENEA-Bologna. The library was processed in ACE format for the MCNP Monte Carlo transport code with the NJOY-94.66 nuclear data processing system.

5. APPLICATION OF THE DATA

This continuous energy cross-section data library for MCNP is in ACE format. The present library was satisfactorily tested in thermal and fast criticality benchmarks. For analyses below 20 MeV, MCB63NEA.BOLlB was applied also in cell and core calculations dedicated to the study of the subcritical accelerator driven systems (ADS). This library provides users an additional ENDF/B-VI based, continuous-energy and multi-temperature library for MCNP with an important feature: there is a perfect consistency with the twin library MCJEFF22NEA.BOLIB already released, in terms of nuclear data processing calculation methodology. Both libraries are based on the NJOY-94.66 data processing system. This may be important, in particular, for the users involved in nuclear data validation who have already used the MCJEF22NEA.BOLIB library.

6. SOURCE AND SCOPE OF DATA

The library is based on the ENDF/B-VI Release 3 evaluated data file. It contains at present 107 isotopes/natural elements, including fission products, processed for up to eight temperatures: 300 K, 500 K, 560 K, 760 K, 800 K, 1000 K, 1500 K and 2200 K. The processed data include gamma-ray and gas production data when available in the specific ENDF/B-VI Release 3 evaluated data files. Thermal scattering cross sections were processed for some of the most important moderator materials using the thermal scattering matrices S (alpha, beta) at various temperatures, included in the original ENDF/B-VI Release 3 thermal scattering law data file.

Nuclides include: H-1, H-2, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, N-14, N-15, O-16, O-17, Na-23, Mg-nat, Al-27, Si-nat, Cl-nat, Ti-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Zr-90, Zr-91, Zr-92, Zr-94, Zr-96, Zr-nat, Nb-93, Mo-94, Mo-95, Mo-96, Mo-97, Mo-nat, Tc-99, Ru-101, Ru-102, Ru-104, Rh-103, Pd-105, Pd-107, Ag-109, I-129, Xe-131, Cs-133, Pr-141, Nd-143, Nd-145, Pm-147, Sm-147, Sm-149, Sm-150, Sm-151, Sm-152, Eu-153, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Hf-nat, Pb-206, Pb-207, Pb-208, Bi-209, Th-232,U-233, U-234, U-235, U-236, U-238, Np-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-242m, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248.

H in CH2 (polyethylene), H in H2O (light water), D in D2O (heavy water), C (graphite),

Be (beryllium metal)

Dosimetry Cross-Sections: 16-S-32, 48-Cd-0, 79-Au-197

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

MAKXSF, which is distributed with the MCNP code package, can be used to convert MCNP Type 1 data to Type 2 (binary). Note that most files have long filenames that do not conform to DOS naming conventions. MAKXSF and MCNP require that filenames conform to DOS conventions.

8. DATA FORMAT AND COMPUTER

ASCII card images; Unix workstation or PC (D00216MNYCP00).

The MCB63 library is distributed as a GNU compressed Unix tar file which can be expanded under Windows with WinZIP8.0 or newer.

9. TYPICAL RUNNING TIME

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

10. REFERENCES

a. Documentation available with library:

R. Orsi, M. Pescarini, A. I. Blokhin and V. Sinitsa, "MCB63NEA.BOLIB - An ENDF/B-VI Release 3 Cross Section Library For the MCNP Monte Carlo Code," ENEA - KT-SCG-00014 (June 28, 2001).

"ZZ-bolibB63.inf," NEA Data Bank information file for NEA-1655/01 (October 2001).

b. Other useful documentation:

J. F. Briesmeister Ed., "MCNP-A General Monte Carlo N-Particle Transport Code, Version 4B," LA-12625-M, Version 4B (March 1997).

R. E. MacFarlane, D. W. Muir, "The NJOY Nuclear Data Processing System," Version 94.66, Los Alamos National Laboratory (December 19, 1996).

R. Orsi, M. Pescarini, A. I. Blokhin, "MCB6.BOLIB An ENDF/B-VI Library for the MCNP Monte Carlo Code," JEF/DOC-766, JEFF Working Group Meeting on Benchmark Testing, Data Processing and Evaluations, NEA Data Bank, Issy-Les-Moulineaux, September 17th - 18th, 1998.

R. Orsi, M. Pescarini, A. I. Blokhin, "MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code," JEF/DOC-779, JEFF Working Group Meeting on Benchmark Testing, Data Processing and Evaluations, NEA Data Bank, Issy-Les-Moulineaux, April 12th - 14th, 1999. ENEA, ERG-SIEC, Internal Report KT-SCG-00004.

N. P. Kocherov, P. K. McLaughlin, "The International Reactor Dosimetry File(IRDF-90 Version 2)," IAEA-NDS-141 Rev. 2 (October 1993).

11. CONTENTS OF LIBRARY

The data libraries and electronic documents in 10.a are transmitted on CD in a GNU compressed tar file, which include data libraries and xsdir files. The uncompressed ASCII files are about 1.3 GB.

12. DATE OF ABSTRACT

December 2003.

KEYWORDS: REACTION CROSS SECTIONS; DOSIMETRY CROSS SECTIONS; MCNP FORMAT; FISSION PRODUCT CROSS SECTIONS