**RSICC DATA PACKAGE DLC-242**

**1. NAME AND TITLE OF DATA LIBRARY**

MATJEFF31.BOLIB: Fine-Group Cross Section Library Based on JEFF3.1 for Nuclear Fission Applications.

**2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS**

BBC: Computer Code for Converting Data to Binary Form and Vice Versa.

BBC is distributed in PSR-317/TRANSX 2.15. TRANSX is a code system developed at LANL to produce neutron, photon, and particle transport tables for discrete-ordinates and diffusion codes from cross sections in MATXS format.

**3. CONTRIBUTORS**

ENEA, Bologna, Italy, through OECD Nuclear Energy Agency Data Bank, Issy-Les Moulineaux, France.

**4. HISTORICAL BACKGROUND AND INFORMATION**

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. It was processed using 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.

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, which was 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, using the NJOY data processing system.

**5. APPLICATION OF THE DATA**

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 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.

**6. SOURCE AND SCOPE OF DATA**

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.

**7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM**

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. The modifications were 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 in the form of updates (upn input file for upd). There is a correction for BBC that fixes some problems with the use of directories. The BBC up7 file can be downloaded from the developer's web site: http://t2.lanl.gov/codes/transx/index.html.

**8. DATA FORMAT AND COMPUTER**

RSICC ID is D00242MNYCP00. NEA PACKAGE-ID is NEA-1847/01

ASCII data; Many Computers.

The present package requires slightly under 1 Gbyte of diskspace.

**9. TYPICAL RUNNING TIME**

Run times vary depending on a number of factors.

**10. REFERENCES**

**a. Documentation available
with library**

/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.

**b. Other useful
documentation**

/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 RSICC or the 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 RSICC or 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 RSICC or 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 RSICC or 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 RSICC or OECD/NEA Data Bank as CCC-0474 MORSE-CGA.

**11. CONTENTS OF LIBRARY**

The package is transmitted on CD in a ZIP file which contains the referenced document listed above in 10.a, ASCII data files, upn update directives for TRANSX 2.15.

**12. DATE OF ABSTRACT**

October 2009.

**KEYWORDS:** COUPLED
NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS; MATXS FORMAT