VITJEFF311.BOLIB : JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Section Library in AMPX Format for Nuclear Fission Applications.
ENEA-Bologna 2007 Revision of SCAMPI, NJOY-99.259 (P480MNYCP00).
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 Group produced the VITJEFF311.BOLIB library in co-operation with a former specialist of the Obninsk Institute of Physics and Power Engineering (IPPE-Obninsk, Russian Federation). The VITJEFF311.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 energy group structure and general features as VITAMIN-B6 and was produced using the same data processing methodologies, based on the NJOY and SCAMPI data processing systems.
VITJEFF311.BOLIB is a pseudo-problem-independent library based on the Bondarenko /10/ (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.
The Fe-56 processed data file was obtained with an additional value (0.01 barns) for the background cross section with respect to the background cross section values used to generate the corresponding data file for VITAMIN-B6. The thermal scattering cross sections were processed at all the temperatures available in the JEFF-3.1.1 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 and VITJEF22.BOLIB /11/), H-2 in heavy water (H2-D2O), C in graphite (C-Gph) and Be in beryllium metal (Be-Th)).
From VITJEFF311.BOLIB it is possible to generate easily, through further proper data processing, working libraries of collapsed and self-shielded cross sections in FIDO-ANISN format (see for example the BUGJEFF311.BOLIB /12/ library) and in AMPX format. The working libraries in AMPX format are used in calculations with the AMPX, SCAMPI and SCALE systems whereas the working libraries in FIDO-ANISN format can be employed, for example, in calculations with the DOORS and PARTISN deterministic transport systems and in calculations with the MORSE Monte Carlo code.
VITJEFF311.BOLIB /1/ is a
multi-group coupled (199 neutron groups + 42 photon groups)
pseudo-problem-independent cross section library in AMPX /2/ format for nuclear
fission applications. VITJEFF311.BOLIB is based on the JEFF-3.1.1 /3/ /4
nuclear data library and it was processed, through the NJOY-99.259 /6/ nuclear
data processing system (including the NEA049 patch) and the ENEA-Bologna 2007
Revision /7/ of the SCAMPI /8/ nuclear data processing system, in the
VITAMIN-B6 /9/ energy group structure using the same methodology and
ORIGINAL NUCLEAR DATA FILE: JEFF-3.1.1
DATA PROCESSING SYSTEMS: NJOY-99.259 (with NEA049 patch) and the ENEA-Bologna 2007 Revision of SCAMPI
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] (same values as in VITAMIN-B6): 300, 600, 1000 and 2100
BACKGROUND CROSS SECTIONS (SIGMA-ZEROs) [barns] (same values as in VITAMIN-B6):
1, 10, 50, 100, 300, 1.0E+3, 1.0E+4, 1.0E+5, 1.0E+6, 1.0E+10 (infinite dilution)
CROSS SECTION LEGENDRE ORDER:
P7 for materials with Z < /= 29 (copper); P5 for the remainder of the nuclides
NUMBER OF MATERIALS: 182
MATERIALS INCLUDED (one file per material):
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
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. VITJEFF311.BOLIB was extensively tested on many thermal, intermediate and fast neutron spectrum criticality safety benchmark experiments.
The problem-dependent data processing must be exclusively performed through the ENEA-Bologna 2007 Revision of the SCAMPI system that can read the binary data files with double precision data generated by NJOY-99.
UNIX workstation, PC, or Mac (D00257MNYCP01).
a. Documentation available with library
M. Pescarini, V. Sinitsa, R. Orsi, “VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications,” ENEA-Bologna Technical Report UTFISSM-P9H6-003_rev1 (March 14, 2013).
The data libraries and documents are transmitted on DVD, which includes data libraries in AMPX format. Uncompressed files are about 442 MB.
KEYWORDS: CROSS SECTIONS, DATA LIBRARY, EVALUATED DATA, MULTIGROUP