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NEA-1869 ZZ-VITJEFF311.BOLIB.

ZZ VITJEFF311.BOLIB, JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Sec Lib in AMPX Fmt for Nuclear Fission Applic.

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1. NAME OR DESIGNATION:  ZZ-VITJEFF311.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-VITJEFF311.BOLIB NEA-1869/02 Tested 03-APR-2013

Machines used:

Package ID Orig. computer Test computer
NEA-1869/02 Linux-based PC Linux-based PC
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3. DESCRIPTION OR FUNCTION

ZZ-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. ZZ-VITJEFF311.BOLIB is based on the JEFF-3.1.1 /3/ /4/ (see also /5/) OECD-NEA Data Bank 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 calculation procedures.

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

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: 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
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.

ZZ-VITJEFF311.BOLIB was extensively tested on many thermal, intermediate and fast neutron spectrum criticality safety benchmark experiments.
NEA-1869/02
NEW VERSION DIFFERS FROM PREVIOUS VERSION
-----------------------------------------
The manual UTFISSM-P9H6-003 has been updated to make several minor corrections and improve the text.
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4. METHODS

The ENEA-Bologna Nuclear Data Group produced the ZZ-VITJEFF311.BOLIB library in co-operation with a former specialist of the Obninsk Institute of Physics and Power Engineering (IPPE-Obninsk, Russian Federation). The ZZ-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.

ZZ-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 ZZ-VITJEF22.BOLIB /11/), H-2 in heavy water (H2-D2O), C in graphite (C-Gph) and Be in beryllium metal (Be-Th)).

From ZZ-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.
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-1869/02 03-APR-2013 Tested at NEADB
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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/  The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD-NEA Data Bank,
     2009.
/4/  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.
/5/  The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD-NEA Data Bank,
     2006.
/6/  R.E. MacFarlane, NJOY-99, "README0", ORNL, RSIC Peripheral Shielding
     Routine Collection PSR-0480/02, December 31, 1999.
/7/  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.
/8/  SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section
     Libraries in AMPX Format, ORNL, RSIC Peripheral Shielding Routine
     Collection PSR-0352/05, September 1995.
/9/  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.
/10/ I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, Group
     Constants for Nuclear Reactors Calculations, Consultants Bureau,
     New York, 1964.
/11/ M. Pescarini, R. Orsi, T. Martinelli, A.I. Blokhin and V. Sinitsa,
     VITJEF22.BOLIB - A JEF-2.2 Multi-Group Coupled (199 n + 42 gamma)
     Cross Section Library in AMPX Format for Nuclear Fission Applications,
     ENEA-Bologna Technical Report FIS-P815-001, April 16, 2003.
/12/ 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-1869/02, included references:
Included in distribution package:
/1/  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 rev.1, March 14, 2013.
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11. HARDWARE REQUIREMENTS:  The present package requires 442 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
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16. MATERIAL AVAILABLE
NEA-1869/02
Information file
README Read-me file with package essential information
ampx\  DIRECTORY containing the ASCII library files
fission_spectra\ DIRECTORY containing total (prompt+delayed) neutron fission
spectra for U-235, U-238, Pu-239 and data related to neutron and photon energy
groups.
chitot_g_U_235_jeff311     Total fission spectrum for U_235
chitot_g_U_238_jeff311     Total fission spectrum for U_238
chitot_g_Pu_239_jeff311    Total fission spectrum for Pu_239
neutron_groups             Neutron group energy and lethargy boundaries
photon_groups              Photon group energy and lethargy boundaries
neutron_weights            Neutron energy group weighting spectrum
photon_weights             Photon energy group weighting spectrum
UTFISSM-P9H6-003_rev1.pdf  VITJEFF311.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.