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NEA-1801 ZZ-VITJEFF31.BOLIB.

ZZ VITJEFF31.BOLIB,JEFF-3.1 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX Fmt for Nuclear Fission Applications

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1. NAME OR DESIGNATION:  ZZ-VITJEFF31.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-VITJEFF31.BOLIB NEA-1801/01 Tested 05-MAR-2008

Machines used:

Package ID Orig. computer Test computer
NEA-1801/01 Linux-based PC Linux-based PC
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3. DESCRIPTION

VITJEFF31.BOLIB /1/ /2/ /3/ is a multigroup coupled (199 neutron groups + 42 photon groups) pseudo-problem-independent cross section library in AMPX /4/ format for nuclear fission applications. VITJEFF31.BOLIB is based on the JEFF-3.1 /3/ /5/ European nuclear data file processed, through the NJOY-99.160 /6/ system with an ENEA-Bologna revised GROUPR module /7/ and the ENEA-Bologna 2007 Revision /8/ of the SCAMPI /9/ system, in the VITAMIN-B6 /10/ energy group structure using the same parameters and calculation procedures.
  
ORIGINAL NUCLEAR DATA FILE: JEFF-3.1
DATA PROCESSING SYSTEMS: ENEA-Bologna Revised Versions of NJOY-99.160 and 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]: 300, 600, 1000, and 2100 (same values as in VITAMIN-B6)
BACKGROUND CROSS SECTIONS (SIGMA-ZEROs) [barns]:
  1, 10, 50, 100, 300, 1.0E+3, 1.0E+4,
  1.0E+5, 1.0E+6, 1.0E+10 (infinite dilution) (same values as in VITAMIN-B6)
LEGENDRE ORDER: P7 for materials with Z < /= 29 (copper); P5 for the remainders
NUMBER OF MATERIALS: 182
MATERIALS INCLUDED: one file per material (nat=natural):
  
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
  
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.
  
VITJEFF31.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 VITJEFF31.BOLIB library in co-operation with a former specialist of the Obninsk Institute of Physics and Power Engineering (IPPE-Obninsk, Russian Federation). The VITJEFF31.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 group structure and the general features as VITAMIN-B6 and was produced using the same data processing methodologies, based on the NJOY and SCAMPI data processing systems.

The ENEA-Bologna Nuclear Data Group performed two important actions to generate the VITJEFF31.BOLIB library.
1) It was prepared a revised version /7/ of the GROUPR module of the NJOY-99.160 system in order to correctly deal with the non Cartesian interpolation schemes contained in 69 JEFF-3.1 evaluated nuclear data files.
2) The ENEA-Bologna 2007 Revision /8/ of the SCAMPI system permits now to read binary files with double precision data generated by NJOY-99 and can prepare total neutron fission spectra from the NJOY GENDF file, differently from the SCAMPI version PSR-0352/04 presently distributed by the OECD/NEA Data Bank. It is noted that, in general, a revision of the SCAMPI system was necessary since the cited version cannot process the JEFF-3.1 evaluated files. It is underlined that the VITJEFF31.BOLIB library package is equipped with the total neutron fission spectra for U-235, U-238 and Pu-239 in tabulated form, differently from the VITAMIN-B6 and VITJEF22.BOLIB /11/ similar libraries, which contain in tabulated form only the prompt components.

VITJEFF31.BOLIB is a pseudo-problem-independent library based on the Bondarenko /12/ (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.

Thermal scattering cross sections were processed at all temperatures available in the JEFF-3.1 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), H-2 in heavy water (H2-D2O), C in graphite (C-GPH) and Be in beryllium metal (Be-TH)).

From VITJEFF31.BOLIB it is easily possible to generate, with the exclusive use of the ENEA-Bologna 2007 Revision of the SCAMPI system, working libraries of collapsed and self-shielded cross sections in AMPX format for calculations with the AMPX, SCAMPI and SCALE systems or in FIDO-ANISN format for calculations with the DOORS, DANTSYS and PARTISN deterministic transport systems and the MORSE  Monte Carlo code.
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8. RELATED OR AUXILIARY PROGRAMS

NJOY-99.160 system with an ENEA-Bologna revised GROUPR module and the ENEA-Bologna 2007 Revision of the SCAMPI system. This revised SCAMPI version will be released in parallel with VITJEFF31.BOLIB in order to permit possible further data processing of the JEFF-3.1 evaluated data files.
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9. STATUS
Package ID Status date Status
NEA-1801/01 05-MAR-2008 Tested at NEADB
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10. REFERENCES

Background references:
/2/  M. Pescarini, V. Sinitsa, R. Orsi:
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Coupled Cross Section Libraries for Nuclear Fission Applications, to be published in the Proceedings of the International Conference on Nuclear Data for Science and Technology, ND-2007, Nice, France, April 22-27, 2007.
  
/3/  A. Koning et al.:
The JEFF Evaluated Nuclear Data Project, to be published in the Proceedings of the International Conference on Nuclear Data for Science and Technology, ND-2007, Nice, France, April 22-27, 2007.
  
/4/  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, ORNL/CSD/TM-283, October 1992. Available from OECD/NEA Data Bank as PSR-0315 AMPX-77.
  
/5/  The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD/NEA Data Bank, 2006.
  
/6/  R.E. MacFarlane, NJOY-99, "README0", PSR-0480/02, December 31, 1999.
  
/7/  V. Sinitsa:
Private Communication, Activity Report of ENEA Research Fellowship, May 31, 2006.
  
/8/  V. Sinitsa, M. Pescarini:
ENEA-Bologna 2007 Revision of the SCAMPI (ORNL) Nuclear Data Processing System, ENEA Internal Report FPN-P9H6-006, September 13, 2007.
  
/9/  SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section Libraries in AMPX Format, Oak Ridge National Laboratory, RSIC Peripheral Shielding Routine Collection PSR-352, September 1995. Available from OECD/NEA Data Bank as PSR-0352 SCAMPI.
  
/10/ 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 National Laboratory, NUREG/CR-6214, Revision 1, 1996. Available from OECD/NEA Data Bank as DLC-0184 ZZ-VITAMIN-B6.
  
/11/ M. Pescarini, R. Orsi, T. Martinelli, A.I. Blokhin and V. Sinitsa:
VITJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications, ENEA Internal Report FIS-P815-001, April 16, 2003.
  
/12/ I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants:
Group Constants for Nuclear Reactors Calculations, published by Consultants Bureau, New York, 1964.
NEA-1801/01, included references:
Included in distribution package:
/1/ M. Pescarini, V. Sinitsa, R. Orsi:
VITJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42 gamma) Cross
Section Library in AMPX Format for Nuclear Fission Applications
ENEA Internal Report FPN-P9H6-007, February 18, 2008
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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 item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

Massimo PESCARINI, Roberto ORSI
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
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16. MATERIAL AVAILABLE
NEA-1801/01
Information file
README: Read-me file with installation and library generalities
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
FPN-P9H6-007_rev0.pdf: VITJEFF31.BOLIB detailed report
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

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