VITJEFF31.BOLIB Multigroup Coupled (199n + 42gamma) X-Section Lib. in AMPX Format for Nuclear Fission Applications.
ENEA-Bologna Revised Versions of NJOY-99.160 and SCAMPI.
ENEA Italian National Agency for New Technologies, Energy and the Environment, Bologna, Italy, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Moulineaux, France.
The ENEA-Bologna Nuclear Data Group produced the VITJEFF31.BOLIB library in cooperation with a specialist of the Obninsk Institute of Physics and Power Engineering (IPPE-Obninsk, Russian Federation). The VITJEFF31.BOLIB library for nuclear fission applications was conceived as the 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 the general features as VITAMIN-B6 and was produced using the same data processing methodologies, based on the NJOY and SCAMPI data processing systems.
VITJEFF31.BOLIB is a multigroup coupled library (199 neutron groups and 42 photon groups) pseudo-problem independent cross section library in AMPX format for nuclear fission applications. VITJEFF31.BOLIB is based on the JEFF-3.1 OECD/NEA Data Bank nuclear data library and it was processed, through the NJOY-99.160 system with an ENEA-Bologna revised GROUPR module and the ENEA-Bologna 2007 Revision of the SCAMPI system, in the VITAMIN-B6 energy group structure using the same parameters and calculation procedures.
ORIGINAL NUCLEAR DATA FILE: JEFF-3.1
DATA PROCESSING SYSTEMS: ENEA-Bologna Revised Versions of NJOY-99.160 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 </= 29 (copper); P5 for the remainders
NUMBER OF MATERIALS: 182
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.
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.
VITJEFF31.BOLIB was extensively tested on many thermal, intermediate and fast neutron spectrum criticality safety benchmark experiments.
The VITJEFF31.BOLIB is based on the ENDF/B-VI Release 3 nuclear data file. The present library has in particular the same group structure and the general features as VITAMIN-B6 and was produced using the same data processing methodologies.
ASCII; CPU INTEL X86
None noted.
a. Documentation
M. Pescarini, V. Sinitsa, and R. Orsi, VITJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications, ENEA Internal Report FPN-P9H6-007, February 18, 2008.
b. Other useful documentation
M. Pescarini, V. Sinitsa, and R. Orsi, “ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications,” in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, editors O. Bersillon, F. Gunsing, E. Bauge, R. Jacqmin, and S. Leray, EDP Sciences, 2008, pp 705–708.
A. Koning et al, “The JEFF Evaluated Nuclear Data Project,” in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, editors O. Bersillon, F. Gunsing, E. Bauge, R. Jacqmin, and S. Leray, EDP Sciences, 2008, pp 721–726.
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, Oak Ridge National Laboratory, October 1992. Also available from OECD/NEA Data Bank as PSR-0315 AMPX-77.
V. Sinitsa, Private Communication, Activity Report of ENEA Research Fellowship, May 31, 2006.
V. Sinitsa, and M. Pescarini, ENEA-Bologna 2007 Revision of the SCAMPI (ORNL) Nuclear Data Processing System, ENEA Internal Report FPN-P9H6-006, September 13, 2007.
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, 1996. Also available from OECD/NEA Data Bank as DLC-0184 ZZ-VITAMIN-B6.
M. Pescarini et al., VITJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199n + 42 gamma) Cross Section Library AMPX Format for Nuclear Fission Applications, ENEA Internal Report FIS-P815-001, April 16, 2003.
I. I. Bondarenko, M. N. Nikolaev, L. P. Abagyan, and N. O. Bazaziants, Group Constants for Nuclear Reactors Calculations, published by Consultants Bureau, New York1964.
SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section Libraries in AMPX Format, Oak Ridge National Laboratory, RSICC Peripheral Shielding Routine Collection PSR-352, September 1995. Available from OECD/NEA Data Bank as PSR-0352 SCAMPI.
This package contains the documentation for the VITJEFF31.BOLIB data library, ASCII library files and a README file. Files are transmitted on one CD in a compressed file format.
January 2010.
KEYWORDS: AMPX INTERFACE FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS