VITJEF22.BOLIB: JEF-2.2 Multigroup Coupled (199n + 42γ) Cross-Section Library in AMPX Format for Nuclear Fission Applications
AIM: Convert AMPX master card-image data to binary format. AIM is not included but is distributed in AMPX, SCALE and SCAMPI packages.
ENEA, Italian National Agency for New Technologies, Energy and the Environment, 'E. Clementel' Research Centre, Bologna, Italy, and Institute of Physics and Power Engineering, Obninsk, Russian Federation, through the OECD Nuclear Energy Agency Data Bank, Issy-les Moulineaux, France.
The ENEA-Bologna Nuclear Data Centre produced the VITJEF22.BOLIB library within the framework of co-operation with specialists of the Obninsk Institute of Physics and Power Engineering (IPPE-Obninsk, Russian Federation). The VITJEF22.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 nuclear data file. 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-94.66 and SCAMPI data processing systems.
From VITJEF22.BOLIB it is possible to easily generate, through further data processing with the AMPX or SCAMPI systems, working libraries of self-shielded cross sections in AMPX or FIDO-ANISN format to be used in transport calculations with the AMPX, SCAMPI, SCALE, DOORS, DANTSYS, and MORSE systems.
ORIGINAL NUCLEAR DATA FILE: JEF-2.2
DATA PROCESSING SYSTEMS: NJOY-94.66 and SCAMPI
FORMAT: AMPX
NUMBER OF GROUPS: 199 neutron groups and 42 photon groups
THERMAL NEUTRON GROUPS: 36 groups below 5.043 eV with upscattering 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 NUMBER OF MATERIALS: 138
MATERIALS INCLUDED: one file per material (nat=natural):
|
|
H-H2O |
H-CH2 |
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.
The prompt 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.
VITJEF22.BOLIB was extensively tested on many thermal and fast criticality benchmark experiments.
VITJEF22.BOLIB in AMPX format (NEA-1699/01) and MATJEF22.BOLIB in MATXS format (NEA-1740/01) are twin libraries produced in ENEA-Bologna and derived from the same set of cross section files in GENDF format, obtained from NJOY-94.66.
VITJEF22.BOLIB is a pseudo-problem-independent library based on the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 133 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 JEF-2.2 thermal scattering law data file for 5 additional bound nuclides (H-1 in light water (H-H2O), H-1 in polyethylene (H-CH2), H-2 in heavy water (H2-D2O), C in graphite (C-GPH) and Be in beryllium metal (Be-TH)).
(RSICC ID: D00241MNYCP00, NEA-1699/01)
Not applicable.
a. Documentation available with library
M. Pescarini, et al., VITJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications, ENEA Internal Report FIS-P815-001, April 16, 2003.
b. Other useful documentation
N. M. Greene, W. E. Ford III, L. M. Petrie, and J. W. Arwood, AMPX-77: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Cross-Section Libraries from ENDF/B-IV and/or ENDF/B-V, ORNL/CSD/TM-283, October 1992.
The JEF-2.2 Nuclear Data Library, JEFF Report 17, OECD/NEA Data Bank, April 2000.
R. E. MacFarlane and D. W. Muir, The NJOY Nuclear Data Processing System, Version 94.66, Los Alamos National Laboratory, December 19, 1996.
SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section Libraries in AMPX Format, Oak Ridge National Laboratory, RSIC Peripheral Shielding Routine Collection PSR-352, September 1995.
J. E. White, et al., 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, 2000.
M. Pescarini, et al., MATJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199n + 42 gamma) Cross Section Library in MATXS Format for Nuclear Fission Applications, ENEA Internal Report FIS-P815-007, June 6, 2004.
I. I. Bondarenko, M. N. Nikolaev, L. P. Abagyan, and N. O. Bazaziants, “Group Constants for Nuclear Reactors Calculations,” translated into English by Consultants Bureau, New York, 1964.
The package is transmitted on a CD which contains the reports listed in section 10.a above, the data files, and test cases.
August 2010
Keywords: CROSS SECTIONS, DATA LIBRARY, EVALUATED DATA, MULTIGROUP