RSICC DATA PACKAGE DLC-261
1. NAME AND TITLE OF DATA LIBRARY
VITENDF70.BOLIB - ENDF/B-VII.0 Multi-Group Coupled (199n +42gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
NJOY-99.259 (with NEA049 patch) and
the ENEA-Bologna 2007 Revision of SCAMPI.
ENEA-Bologna Nuclear Data Group,
Bologna, Italy through the OECD Nuclear Energy Agency Data Bank,
4. HISTORICAL BACKGROUND AND INFORMATION
is a multi-group coupled (199 neutron groups + 42 photon groups) pseudo-problem-independent
cross section library in AMPX format for nuclear fission applications.
VITENDF70.BOLIB is based on the ENDF/B-VII.0 evaluated nuclear data library and
it was processed, through the NJOY-99.259 nuclear data processing system
(including the NEA049 patch) and the ENEA-Bologna 2007 Revision of the SCAMPI nuclear
data processing system, in the VITAMIN-B6 energy group structure using the same
methodology and calculation procedures.
same approach was also followed to get the VITJEFF311.BOLIB library, twin
library of VITENDF70.BOLIB, based on the JEFF-3.1.1 OECD-NEA Data Bank
evaluated nuclear data library.
5. APPLICATION OF THE DATA
ENEA-Bologna Nuclear Data Group produced the VITENDF70.BOLIB library in
co-operation with a former specialist of the Obninsk Institute of Physics and
Power Engineering (IPPE-Obninsk, Russian Federation). 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.
underlined that VITENDF70.BOLIB and the ORNL VITAMIN-B7 similar library are
both based on the ENDF/B-VII.0 evaluated nuclear data library but, differently
from VITENDF70.BOLIB generated with NJOY-99.259, VITAMIN-B7 was processed with
the ORNL AMPX-6.1 nuclear data processing system.
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 177 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 ENDF/B-VII.0 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), H-2 in heavy water
(H2-D2O), C in graphite (C-Gph) and Be in beryllium metal (Be-Th)).
VITENDF70.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 broad-group working
library obtained through cross section collapsing of the fine-group
VITJEFF311.BOLIB 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. This 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.
6. SOURCE AND SCOPE OF DATA
NUCLEAR DATA FILE: ENDF/B-VII.0
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
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: 183
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-69 Ga-71 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:
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
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.
VITENDF70.BOLIB was extensively tested on many thermal, intermediate and fast
neutron spectrum criticality safety benchmark experiments.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
NJOY-99.259 (with NEA049 patch) and
the ENEA-Bologna 2007 Revision of the SCAMPI system.
8. DATA FORMAT AND COMPUTER
PC Windows and Linux (D00261PCX8600).
9. TYPICAL RUNNING TIME
Pescarini, V. Sinitsa, R. Orsi, M. Frisoni, “VITENDF70.BOLIB - An
ENDF/B-VII.0 Multi-Group Coupled (199 n + 42 gamma) Cross Section Library
in AMPX Format for Nuclear Fission Applications”, ENEA-Bologna Technical
Report UTFISSM-P9H6-005, May 25, 2012.
Greene, W.E. Ford III, L.M. Petrie, 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, Oak Ridge, ORNL Report
ORNL/CSD/TM-283, October 1992.
Chadwick et al., ENDF/B-VII.0: Next Generation Evaluated Nuclear
Data Library for Nuclear Science and Technology, Nuclear Data Sheets,
Volume 107, Number 12, pp. 2931-3060, December 2006.
MacFarlane, NJOY-99, "README0", ORNL, RSIC Peripheral Shielding
Routine Collection PSR-0480/02, December 31, 1999.
Sinitsa, M. Pescarini, ENEA-Bologna 2007 Revision of the SCAMPI (ORNL)
Nuclear Data Processing System, ENEA-Bologna Internal Technical Report
FPN-P9H6-006, September 13, 2007.
Collection of Codes for Manipulating Multigroup Cross Section
Libraries in AMPX Format, ORNL, RSIC Peripheral Shielding Routine
Collection PSR-0352/05, September 1995.
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,
ORNL Report ORNL-6795/R1, NUREG/CR-6214, Revision 1, January 1995.
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, November 10, 2011.
JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD-NEA Data Bank,
Koning, E. Bauge, C.J. Dean, E. Dupont, U. Fischer, R.A. Forrest,
R. Jacqmin, H. Leeb, M.A. Kellet, R.W. Mills, C. Nordborg, M. Pescarini,
Y. Rugama, P. Rullhusen, Status of the JEFF Nuclear Data Library,
Proceedings of the International Conference on Nuclear Data for Science
and Technology (ND-2010), Jeju Island, Korea, April 26-30, 2010.
JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD-NEA Data Bank,
Risner, D. Wiarda, M.E. Dunn, T.M. Miller, D.E. Peplow, B.W. Patton,
Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7
Broad-Group Coupled Neutron/Gamma Cross-Secion Libraries Derived from
ENDF/B-VII.0 Nuclear Data, Oak Ridge, ORNL Report ORNL/TM-2011/12,
NUREG/CR-7045, September 2011.
Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, Group
Constants for Nuclear Reactors Calculations, Consultants Bureau,
New York, 1964.
Pescarini, V. Sinitsa, R. Orsi, M. Frisoni, BUGJEFF311.BOLIB A
JEFF-3.1.1 Broad-Group Coupled (47 n + 20 gamma) Cross Section Library
in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry
Applications, ENEA-Bologna Technical Report UTFISSM-P9H6-002, May 12,
The VITENDF70.BOLIB package is
transmitted on CD and includes the referenced document along with the data files.
12. DATE OF ABSTRACT
KEYWORDS: CROSS SECTIONS,
DATA LIBRARY, EVALUATED DATA, MULTIGROUP