NEA-1847 ZZ-MATJEFF31.BOLIB.

1. NAME OR DESIGNATION:  ZZ-MATJEFF31.BOLIB

3. DESCRIPTION

MATJEFF31.BOLIB /1/ is a multi-group coupled (199 neutron groups + 42 photon groups) pseudo-problem-independent cross section library in MATXS format for nuclear fission applications. MATJEFF31.BOLIB is based on the JEFF-3.1 /2/ OECD/NEA Data Bank evaluated nuclear data library and it was processed, through the NJOY-99 /3/ system, in the VITAMIN-B6 /4/ library group structure using the same calculation methodology.
  
Since the data processing of MATJEFF31.BOLIB was performed before the release of the JEFF-3.1.1 /5/ evaluated nuclear data library, at the end of February 2009, an additional separated set of JEFF-3.1.1 processed data files was recently included for the following 12 nuclides, obtained for consistency with the same NJOY version previously used: O-16, Cl-35, Ca-46, Cr-52, Fe-56, Zr-91, Zr-96, Mo-95, Eu-154, U-233, Np-237 and Pu-239. Concerning this additional set of JEFF-3.1.1 data files, it was decided to reprocess only the nuclides already inserted in the list of processed files for MATJEFF31.BOLIB whose evaluations were updated or corrected in the JEFF-3.1.1 library. MATJEFF31.BOLIB was extensively tested on many thermal, intermediate and fast neutron spectrum criticality safety benchmark experiments.
  
ORIGINAL NUCLEAR DATA FILE: JEFF-3.1 + JEFF-3.1.1
DATA PROCESSING SYSTEMS: NJOY-99.160(GROUPR module modified by ENEA-Bologna)
FORMAT: MATXS
NUMBER OF GROUPS: 199 neutron groups and 42 photon groups
THERMAL NEUTRON GROUPS: 36 groups below 5.043 eV with upscatter cross sections
NEUTRON ENERGY RANGE: 1.0E-5 eV - 19.64 MeV
PHOTON ENERGY RANGE: 1.0 keV - 30.0 MeV
TEMPERATURES [K]: 300, 600, 1000, and 2100 (same values as in VITAMIN-B6)
BACKGROUND CROSS SECTIONS (SIGMA-ZEROs) [barns]:
1, 10, 50, 100, 300, 1.0E+3, 1.0E+4,1.0E+5, 1.0E+6, 1.0E+10 (infinite dilution)
(same values as in VITAMIN-B6)
LEGENDRE ORDER: P7 for materials with Z < /= 29 (copper); P5 for the remainders
NUMBER OF MATERIALS: 182 nuclides
MATERIALS INCLUDED: one file per material (nat=natural):
  
H-H2O    H-CH2    H-ZrH    D-D2O    H-3      He-3     He-4     Li-6     
Li-7     Be-9     Be-TH    B-10     B-11     C-nat    C-GPH    N-14     
N-15     O-16     O-17     F-19     Na-23    Mg-24    Mg-25    Mg-26    
Al-27    Si-28    Si-29    Si-30    P-31     S-32     S-33     S-34     
S-36     Cl-35    Cl-37    K-39     K-40     K-41     Ca-40    Ca-42    
Ca-43    Ca-44    Ca-46    Ca-48    Ti-46    Ti-47    Ti-48    Ti-49    
Ti-50    V-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    Cu-63    Cu-65    Ga-nat   Y-89     Zr-90    Zr-91    Zr-92    
Zr-94    Zr-96    Nb-93    Mo-92    Mo-94    Mo-95    Mo-96    Mo-97    
Mo-98    Mo-100   Ag-107   Ag-109   Cd-106   Cd-108   Cd-110   Cd-111   
Cd-112   Cd-113   Cd-114   Cd-115m  Cd-116   In-113   In-115   Sn-112   
Sn-114   Sn-115   Sn-116   Sn-117   Sn-118   Sn-119   Sn-120   Sn-122   
Sn-123   Sn-124   Sn-125   Sn-126   Ba-138   Eu-151   Eu-152   Eu-153   
Eu-154   Eu-155   Gd-152   Gd-154   Gd-155   Gd-156   Gd-157   Gd-158   
Gd-160   Er-162   Er-164   Er-166   Er-167   Er-168   Er-170   Hf-174   
Hf-176   Hf-177   Hf-178   Hf-179   Hf-180   Ta-181   Ta-182   W-182    
W-183    W-184    W-186    Re-185   Re-187   Au-197   Pb-204   Pb-206   
Pb-207   Pb-208   Bi-209   Th-230   Th-232   Pa-231   Pa-233   U-232    
U-233    U-234    U-235    U-236    U-237    U-238    Np-237   Np-238   
Np-239   Pu-236   Pu-237   Pu-238   Pu-239   Pu-240   Pu-241   Pu-242   
Pu-243   Pu-244   Am-241   Am-242   Am-242m  Am-243   Cm-241   Cm-242   
Cm-243   Cm-244   Cm-245   Cm-246   Cm-247   Cm-248
  
NEUTRON WEIGHTING SPECTRUM:
  
Corresponding to the IWT=4 input option in the GROUPR module of NJOY:
from 1.0E-5 eV to 0.125 eV -> Maxwellian thermal spectrum (kT = 0.025 eV)
from 0.125 eV to 820.8 keV  -> '1/E' slowing-down spectrum
from 820.8 keV to 19.64 MeV -> fission spectrum (fission temperature = 1.273 MeV)
  
PHOTON WEIGHTING SPECTRUM:
  
Corresponding to the IWT=3 input option in the GAMINR module of NJOY:
'1/E' spectrum with a 'roll-off' at lower energies to represent photoelectric absorption and a similar 'drop-off' at higher energies corresponding to the Q-value for neutron capture.
  
TABULATED DATA
  
The total (prompt + delayed) neutron fission spectra for U-235, U-238 and Pu-239 are included in tabulated form in the package together with the neutron and photon group energy boundaries, the neutron and photon group lethargy boundaries and the neutron and photon group lethargy widths.
The neutron and photon energy weighting spectra in group representation are also included in the package.
  
Detector response functions are at present not included in the library package.

4. METHODS

The ENEA-Bologna Nuclear Data Group produced the MATJEFF31.BOLIB library in co-operation with a specialist, formerly at the Obninsk Institute of Physics and Power Engineering (IPPE-Obninsk, Russian Federation). The MATJEFF31.BOLIB library for nuclear fission applications was conceived as a European counterpart of the VITAMIN-B6 American library, based on the ENDF/B-VI Release 3 evaluated data library. The present library has in particular the same group structure and general features as VITAMIN-B6 and was produced using the same data processing methodologies, based on the NJOY data processing system.
  
The NJOY-99.160 data processing system was used for the MATJEFF31.BOLIB library generation to assure the consistency with the previous generation of the VITJEFF31.BOLIB /6/ twin library, based on the same GENDF cross section data file. In particular it was used a revised version of the GROUPR /7/ module, originally developed in ENEA-Bologna before the free release of an analogous GROUPR revised version with NJOY-99.161, in order to correctly deal with the non Cartesian interpolation schemes, contained in 69 JEFF-3.1 evaluated nuclear data files.
  
The TRANSX-2.15 /8/ code was then used to obtain the total (prompt + delayed) fission spectra for U-235, U-238 and Pu-239. These data, contained in the MATJEFF31.BOLIB package, are available in tabulated form as in the VITJEFF31.BOLIB library package. On the contrary the VITAMIN-B6, VITJEF22.BOLIB /9/ and MATJEF22.BOLIB /10/ similar library packages contain in tabulated form only the prompt components.
  
MATJEFF31.BOLIB is a pseudo-problem-independent library based on the Bondarenko /11/ (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 176 nuclides at 4 temperatures, obtained for the most part with 6 to 8 values for the background cross section.
Thermal scattering cross sections were processed at all temperatures available in the JEFF-3.1 thermal scattering law data file for 6 additional bound nuclides (H-1 in light water (H-H2O), H-1 in polyethylene (H-CH2), H-1 in zirconium hydride (H-ZrH) (not contained in VITAMIN-B6, VITJEF22.BOLIB and MATJEF22.BOLIB), H-2 in heavy water (H2-D2O), C in graphite (C-GPH) and Be in beryllium metal (Be-TH)).
  
From MATJEFF31.BOLIB it is easily possible to generate, with the use of the TRANSX code, working libraries of collapsed and self-shielded cross sections in GOXS or FIDO-ANISN format for  calculations with the DOORS /12/, DANTSYS /13/ and PARTISN /14/ deterministic transport systems and the MORSE /15/ Monte Carlo code.

8. RELATED OR AUXILIARY PROGRAMS

To obtain collapsed and self-shielded cross section working libraries in various formats (e.g. GOXS and FIDO-ANISN) for the specific applications an updated version of the PSR-0317 TRANSX 2.15 code is needed which was developed in ENEA-Bologna. In particular this revised version can produce GOXS binary data files in double precision and can perform the self-shielding for damage-energy cross sections and KERMA factors. The cited updating of TRANSX-2.15 is included in this package.

10. REFERENCES

Included in NEA-1847/01 distribution package:
  
/1/ M. Pescarini, V. Sinitsa, R. Orsi, MATJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42 gamma) Cross Section Library in MATXS Format for Nuclear Fission Applications, ENEA Internal Report FPN-P9H6-014, May 5, 2009. Available from OECD/NEA Data Bank as NEA-1801/01 ZZ MATJEFF31.BOLIB.
Background references:
  
/2/ The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD/NEA Data Bank, 2006.
  
/3/ R.E.MacFarlane, NJOY-99, "README0", PSR-0480/02, December 31, 1999.
  
/4/ J.E. White, D.T. Ingersoll, R.Q. Wright, H.T. Hunter, C.O. Slater, N.M. Greene, R.E. MacFarlane, R.W. Roussin, Production and Testing of the Revised VITAMIN-B6 Fine-Group and the BUGLE-96 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI.3 Nuclear Data, Oak Ridge National Laboratory, NUREG/CR-6214, Revision 1, ORNL-6795/R1, 1996. Available from OECD/NEA Data Bank as DLC-0184/ ZZ VITAMIN-B6.
  
/5/ The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD/NEA Data Bank, 2009.
  
/6/ M. Pescarini, V. Sinitsa, R. Orsi, VITJEFF31.BOLIB - A JEFF-3.1 Multigroup Coupled (199 n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications, ENEA FPN-P9H6-007, February 18, 2008. Available from OECD/NEA Data Bank as NEA-1801/01 ZZ VITJEFF31.BOLIB.
  
/7/ V. Sinitsa, Private Communication, Activity Report of ENEA Research Fellowship, May 31, 2006.
  
/8/ TRANSX 2.15: Code System to Produce Neutron, Photon, and Particle Transport Tables for Discrete-Ordinates and Diffusion Codes from Cross Sections in MATXS Format, RSIC Peripheral Shielding Routine Collection PSR-317, February 1995. Available from OECD/NEA Data Bank as PSR-0317 TRANSX 2.15.
  
/9/ M. Pescarini, R. Orsi, T. Martinelli, A.I. Blokhin, V. Sinitsa, VITJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199 n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications, ENEA FIS-P815-001, April 16, 2003. Available from OECD/NEA Data Bank as NEA-1699/01 ZZ-VITJEF22.BOLIB.
  
/10/ M. Pescarini, R. Orsi, T. Martinelli, A.I. Blokhin, V. Sinitsa, MATJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199 n + 42 gamma) Cross Section Library in MATXS Format for Nuclear Fission Applications, ENEA FIS-P815-007, June 6, 2004. Available from OECD/NEA Data Bank as NEA-1740/01 ZZ-MATJEF22.BOLIB.

/11/ I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, Group Constants for Nuclear Reactors Calculations, Consultants Bureau, New York, 1964.
  
/12/ DOORS3.1: One-, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System, ORNL, RSIC Computer Code Collection CCC-650, August 1996. Available from OECD/NEA Data Bank as CCC-0650/04 DOORS-3.2A.
  
/13/ DANTSYS 3.0: One-, Two-, and Three-Dimensional, Multigroup, Discrete Ordinates Transport Code System, ORNL, RSIC Computer Code Collection CCC-547, August 1995.
  
/14/ R.E. Alcouffe, R.S. Baker, J.A. Dahl, S.A. Turner, R. Ward, PARTISN: A Time-Dependent, Parallel Neutral Particle Transport Code System, LA-UR-05-3925, May 2005. Available from OECD/NEA Data Bank as CCC-0707/02 PARTISN-4.00.
  
/15/ M.B. Emmet, The MORSE Monte Carlo Radiation Transport Code System, Oak Ridge National Laboratory, ORNL-4972, February 1975; ORNL-4972/R1, February 1983; ORNL-4972/R2, July1984; ORNL-4972/R3 draft, June 1993. Available from OECD/NEA Data Bank as CCC-0474 MORSE-CGA.

11. HARDWARE REQUIREMENTS

The present package requires slightly under 1 Gbytes of diskspace.

15. NAME AND ESTABLISHMENT OF AUTHORS

    M. Pescarini, R. Orsi
    ENEA
    Italian National Agency for New Technologies, Energy and the Environment  
    "E. Clementel" Research Centre
    Bologna, Italy

    V. Sinitsa
    ENEA Consultant, formerly at IPPE
    Institute of Physics and Power Engineering
    Obninsk, Russian Federation

MATJEFF31.BOLIB-INFO.FIL: Information file
README: Read-me file with installation and library generalities
matxs: DIRECTORY containing the ASCII library files
fission_spectra: Directory containing total neutron fission spectra for U-235,
U-238, Pu-239 and data related to neutron and photon energy groups
FPN-P9H6-014.pdf: MATJEFF31.BOLIB detailed report
upn.TRANSX-2.15_bo  Updating of the TRANSX-2.15 code (developed by the
ENEA-Bologna)