Computer Programs
NEA-1891 ZZ-VITJEFF32.BOLIB.
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NEA-1891 ZZ-VITJEFF32.BOLIB.

ZZ-VITJEFF32.BOLIB, JEFF-3.2 Multi-Grp Coupled (199n+ 42gamma) X-Sec. Lib. in AMPX Fmt for Nuclear Fission Applications

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1. NAME OR DESIGNATION

ZZ-VITJEFF32.BOLIB

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
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
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3. DESCRIPTION OR FUNCTION

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.

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4. METHODS

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.

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8. RELATED OR AUXILIARY PROGRAMS

NJOY-2012.53 and the ENEA-Bologna 2007 Revision of the SCAMPI system.

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9. STATUS
Package ID Status date Status
NEA-1891/01 18-MAR-2016 Screened
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10. 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/  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).

NEA-1891/01, included references:
/1/  M. Pescarini, R. Orsi, M. Frisoni, VITJEFF32.BOLIB - A JEFF-3.2
     Multi-Group Coupled (199 n + 42 gamma) Cross Section Library in AMPX
     Format for Nuclear Fission Applications, ENEA-Bologna Technical Report
     SICNUC-P9H6-002, February 1, 2016.
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11. HARDWARE REQUIREMENTS

The present package requires 578 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

 

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-1891/01
VITJEFFF32.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;
SICNUC-P9H6-002.pdf: VITJEFF32.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.