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NEA-1870 ZZ-VITENDF70.BOLIB.

ZZ VITENDF70.BOLIB, ENDF/B-VII.0 Multi-Grp Coupled (199n +42gamma)X-Sec.Lib.in AMPX Fmt for Nuclear Fission Applications

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1. NAME OR DESIGNATION:  ZZ-VITENDF70.BOLIB
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-VITENDF70.BOLIB NEA-1870/01 Tested 04-JUL-2012

Machines used:

Package ID Orig. computer Test computer
NEA-1870/01 Linux-based PC,PC Windows Linux-based PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

VITENDF70.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. VITENDF70.BOLIB is based on the ENDF/B-VII.0 /3/ evaluated nuclear data library and it was processed, through the NJOY-99.259 /4/ nuclear data processing system (including the NEA049 patch) and the ENEA-Bologna 2007 Revision /5/ of the SCAMPI /6/ nuclear data processing system, in the VITAMIN-B6 /7/ energy group structure using the same methodology and calculation procedures.

The same approach was also followed to get the VITJEFF311.BOLIB /8/ library, twin library of VITENDF70.BOLIB, based on the JEFF-3.1.1 /9//10/ (see also /11/) OECD-NEA Data Bank evaluated nuclear data library.

ORIGINAL NUCLEAR DATA FILE: ENDF/B-VII.0

DATA PROCESSING SYSTEMS: NJOY-99.259 (with NEA049 patch) 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] (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

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.

VITENDF70.BOLIB was extensively tested on many thermal, intermediate and fast neutron spectrum criticality safety benchmark experiments.
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4. METHODS

The 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.

It is underlined that VITENDF70.BOLIB and the ORNL VITAMIN-B7 /12/ 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.

VITENDF70.BOLIB is a pseudo-problem-independent library based on the Bondarenko /13/ (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)).

From 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 /14/ 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.
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8. RELATED OR AUXILIARY PROGRAMS

NJOY-99.259 (with NEA049 patch) and the ENEA-Bologna 2007 Revision of the SCAMPI system.
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9. STATUS
Package ID Status date Status
NEA-1870/01 04-JUL-2012 Screened
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10. REFERENCES

Background references:
/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/  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.
/4/  R.E. MacFarlane, NJOY-99, "README0", ORNL, RSIC Peripheral Shielding
     Routine Collection PSR-0480/02, December 31, 1999.
/5/  V. 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.
/6/  SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section
     Libraries in AMPX Format, ORNL, RSIC Peripheral Shielding Routine
     Collection PSR-0352/05, September 1995.
/7/  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.
/8/  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, November 10, 2011.
/9/  The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD-NEA Data Bank,
     2009.
/10/ A.J. 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.
/11/ The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD-NEA Data Bank,
     2006.
/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-Secion Libraries Derived from
     ENDF/B-VII.0 Nuclear Data, Oak Ridge, ORNL Report ORNL/TM-2011/12,
     NUREG/CR-7045, September 2011.
/13/ I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, Group
     Constants for Nuclear Reactors Calculations, Consultants Bureau,
     New York, 1964.
/14/ M. 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,
     2011.
NEA-1870/01, included references:
Included in distribution package:
/1/  M. 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.
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11. HARDWARE REQUIREMENTS:  The present package requires 444 Mbytes of diskspace.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Massimo PESCARINI
ENEA Italian National Agency for New Technologies, Energy and the Environment
'E.Clementel' Research Centre
Bologna, Italy

Valentin SINITSA
ENEA Consultant,
formerly at IPPE, Institute of Physics and Power Engineering
Obninsk, Russian Federation

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
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16. MATERIAL AVAILABLE
NEA-1870/01
VITENDF70.BOLIB-INFO.FIL: Information file
README: Read-me file with package essential information
ampx: directory containing the ASCII library files
fission_spectra: directory containing the total (prompt + delayed) neutron
                 fission spectra for U-235, U-238, Pu-239 and the data
                 related to neutron and photon energy groups
UTFISSM-P9H6-005_rev0.pdf: VITENDF70.BOLIB user's manual
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: cross sections, data library, evaluated data, multigroup.