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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-VITJEFF32.BOLIB | NEA-1891/01 | Tested | 18-MAR-2016 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1891/01 | Linux-based PC | Linux-based PC |
VITJEFF32.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. VITJEFF32.BOLIB is based on the
JEFF-3.2 /3//4//5//6//7/ OECD-NEA Data Bank nuclear data library and it was processed through the LANL NJOY-2012.53 /8/ nuclear data processing system and the ENEA-Bologna 2007 Revision /9/ of the ORNL SCAMPI /10/ nuclear data processing system in the VITAMIN-B6 /11/ energy group structure using the same methodology and calculation procedures.
ORIGINAL NUCLEAR DATA FILE: JEFF-3.2
DATA PROCESSING SYSTEMS: NJOY-2012.53 and the
ENEA-Bologna 2007 Revision of 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] (same values as in VITAMIN-B6): 300, 600, 1000 and 2100
BACKGROUND CROSS SECTIONS (SIGMA-ZEROs) [barns]
1.0E-6 (total self-shielding), 1.0E-2, 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 </= 30 (zinc);
P5 for the remainder of the nuclides
NUMBER OF MATERIALS: 190
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 O-18 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 Zn-64 Zn-66 Zn-67 Zn-68
Zn-70 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-180 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
nat=natural element
Gph=graphite
Th=thermal
D=H2=deuterium
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.
FURTHER INFORMATION:
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.
VITJEFF32.BOLIB was extensively tested on many thermal, intermediate and fast neutron spectrum criticality safety benchmark experiments.
The VITJEFF32.BOLIB library for nuclear fission applications was conceived as a European counterpart of the ORNL VITAMIN-B6 and VITAMIN-B7 /12/ American libraries, respectively based on the US ENDF/B-VI.3 /13/ and ENDF/B-VII.0 /14/ evaluated data libraries. 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.
VITJEFF32.BOLIB is a pseudo-problem-independent library based on the Bondarenko /15/ (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 184 standard (not bound) nuclides processed at 4 temperatures and 12 background cross sections. Concerning the used background cross section values, a conservative choice was performed with respect to both VITAMIN-B6 and VITAMIN-B7 libraries. In particular the followed approach (the same background cross section set of 12 values for each standard nuclide) was more similar to that employed in the VITAMIN-B7 generation but, in addition to the values used for the data processing of VITAMIN-B7, the 1.0E-6 and 0.01 values were included. In particular the 1.0E+10 value corresponds to the infinite dilution cross section whereas 1.0E-06 represents the total self-shielding value. The 1.0E-6 value was chosen as near as possible to 0. (in line with the values used in the past for getting close to 0.), according to the previously generated OECD-NEADB VITAMIN-J /16/ library. Concerning the 0.01 value, it is underlined that this additional background cross section value improves further (see /17/), for example, the neutron cross section self-shielding of Fe-56 in natural iron and of Co-59 (only isotope in natural cobalt), through a more precise self-shielding factor interpolation.
The thermal scattering cross sections were processed at all the temperatures available in the JEFF-3.2 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), H-2 in heavy water (H2-D2O), C in graphite (C-Gph) and Be in beryllium metal (Be-Th)).
From VITJEFF32.BOLIB it is possible to generate easily, through further proper data processing, working libraries of collapsed and self-shielded cross sections in AMPX format and in FIDO-ANISN 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 and NJOY-2012.
/2/ N.M. 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.
/3/ O. Cabellos, Processing and Benchmarking of the JEFF32T4 (JEFF-3.2)
Library (24th February 2014 Update), OECD-NEA Data Bank, JEF/DOC-1562,
November 2013.
/4/ A. Stankovskiy, SCK-CEN Experience from Processing, Benchmarking and
Application of JEFF-3.2, OECD-NEA Data Bank JEF/DOC-1608, November 2014.
/5/ Y. Peneliau, JEFF-3.2T3 Benchmarking - Criticality Experiments to Full
Reactor Calculations, OECD-NEA Data Bank JEF/DOC-1583, April 2014.
/6/ O. Cabellos, Processing and Validation of the Neutron Cross-Section Test
Library JEFF-3.2-T3, OECD-NEA Data Bank JEF/DOC-1516, November 2013.
/7/ J. Kopecky, Final Verification and Validation of JEFF-3.2, OECD-NEA
Data Bank JEF/DOC-1590, November 2014.
/8/ R.E. MacFarlane, D.W. Muir, R.M. Boicourt, A.C. Kahler, The NJOY Nuclear
Data Processing System, Version 2012, LA-UR-12-27079 Rev, Updated for
NJOY2012.50, February 12,2015.
/9/ V. Sinitsa, M. Pescarini, ENEA-Bologna 2007 Revision of the SCAMPI (ORNL)
Nuclear Data Processing System, ENEA-Bologna Technical Report
FPN-P9H6-006, September 13, 2007.
/10/ SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section
Libraries in AMPX Format, ORNL, RSIC Peripheral Shielding Routine
Collection PSR-0352, September 1995. Available from OECD-NEA Data Bank
as PSR-0352/06 SCAMPI, corresponding to the last version of the
ENEA-Bologna 2007 Revision (see /9/), July 7, 2015.
/11/ 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,
ORNL Report ORNL-6795/R1, NUREG/CR-6214, Revision 1, January 1995.
/12/ J.M. 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-Section Libraries Derived from
ENDF/B-VII.0 Nuclear Data, Oak Ridge, ORNL Report ORNL/TM-2011/12,
NUREG/CR-7045, September 2011.
/13/ P.F. Rose, ENDF/B-VI Summary Documentation, Brookhaven National
Laboratory, BNL-NCS-17541 (ENDF-201) 4th Edition, October 1991.
/14/ M.B. 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.
/15/ I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, Group
Constants for Nuclear Reactors Calculations, Consultants Bureau,
New York, 1964.
/16/ E. Sartori, VITAMIN-J, a 175 Group Neutron Cross Section Library Based on
JEF-1 for Shielding Benchmark Calculations, OECD-NEA Data Bank,
JEF/DOC-100 Preliminary, October 1985.
/17/ C. Konno, K. Takakura, K. Kondo, S. Ohnishi, K. Ochiai and S. Sato,
Important Remarks on Latest Multigroup Libraries, Progress in Nuclear
Science and Technology, Vol. 2,pp.341-345 (2011).
Massimo PESCARINI
ENEA Italian National Agency for New Technologies, Energy and the Environment
'E.Clementel' Research Centre
Bologna, Italy
Roberto ORSI
ENEA Italian National Agency for New Technologies, Energy and the Environment
'E.Clementel' Research Centre
Bologna, Italy
Manuela FRISONI
ENEA Italian National Agency for New Technologies, Energy and the Environment
'E.Clementel' Research Centre
Bologna, Italy
Keywords: cross sections, data library, evaluated data, multigroup.
