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NEA-1822 ZZ-FLUKA05-PRE-LIB.

ZZ FLUKA05-PRE-LIB, FLUKA05 Multi-group, multi-purpose nuclear data library, neutrons, photons, charged particles

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1. NAME OR DESIGNATION:  ZZ-FLUKA05-PRE-LIB.
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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-FLUKA05-PRE-LIB NEA-1822/01 Tested 01-OCT-2008

Machines used:

Package ID Orig. computer Test computer
NEA-1822/01 Linux-based PC,PC Windows PC Windows
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3. DESCRIPTION

During the preparation of the FLUKA05 Multi-group Nuclear Data Library, distributed with FLUKA, several working files have been produced; among them a GENDF and a DTF formatted library. These aim at an enlarged group of users for use with other computer codes than FLUKA.
  
The main features of the library include:
- Source of the data: many (see below);
- Processing code: all the computations have been carried out by NJOY 99.259 with some minor modifications to speed up the handling of the data: modifications include:
   - enlargement of some arrays;
   - addition of a built in weighting function (see below);
- Number of neutron groups: 260 in the range 1.0E-05 eV to 20.0E+06 eV, but for materials picked up from ENDL-78 (see attached list) the lower limit of the lowest energy group is 1.0E-04;
- Number of photon groups: corresponding to igg=10 option of the NJOY module GROUPR, i.e. VITAMIN-j 42-group structure  from 1.0E+03 eV to 50.0E+6 eV;
- Thermal neutron groups: 31 below 3.0592 eV with upscattering;
- Reference temperatures (K): 87 and 296.3;
- Background cross sections: 0 and infinity (1.0E-06 and 1.0e+10, respectively);
- Legendre order: P5;
- Neutron weighting function: Maxwellian from 0 to EKT, where EKT is a temperature
         dependent energy;
         1/E from EKT to 20.0E-06 Ev;
Note that this spectrum corresponds to the iwt=7 weighting function option of GROUPR, but the 1/E section is extended up to 20.0e+06 eV.
  
The library is written in ASCII, so as to reach the maximum portability. The library is available in two versions: GENDF, the NJOY GROUPR output format, and DTF fixed FIDO format.
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4. METHODS

Additional features of the library include:
- total and partial kerma
- gas production data
- charged particle scattering matrices
The library includes 230 materials (isotopes, elements and molecules). The source of the data is extremely large: from the worldwide available libraries of evaluated data a selection has been performed to choose for each material the most reliable version in view of the utilization of the library: a large number of materials come from ENDF/B (various releases), JEF(id.), JEFF(id.) and JENDL(id.). The list of the materials is as follows:
  
Material  Source        Material  Source        Material  Source
Ag-107  ENDF/B-VI 7.0   Gd-nat  ENDL-78         Pb-208  ENDF/B-VI 6.8
Ag-109  ENDF/B-VI 7.0   Ge-70   ENDF/B-VI 7.0   Pd-102  ENDF/B-VI 6.8
Al-27   ENDF/B-VI 6.8   Ge-72   ENDF/B-VI 7.0   Pd-104  ENDF/B-VI 6.8
Am-241  ENDF/B-VI 6.8   Ge-73   ENDF/B-VI 7.0   Pd-105  ENDF/B-VI 6.8
Am-243  ENDF/B-VI 6.8   Ge-74   ENDF/B-VI 7.0   Pd-106  ENDF/B-VI 6.8
Ar-36   JEFF 3.1        Ge-76   ENDF/B-VI 7.0   Pd-108  ENDF/B-VI 6.8
Ar-38   JEFF 3.1        H-1     ENDF/B-VI 7.0   Pd-110  ENDF/B-VI 6.8
Ar-40   JEFF 3.1        H-2     ENDF/B-VI 7.0   Pu-239  ENDF/B-VI 6.8
Ar-nat  ENDL-78         H-3     ENDF/B-VI 7.0   Re-185  ENDL-78      
As-75   ENDF/B-VI 7.0   H-CH2   ENDF/B-VI 7.0   Re-187  ENDL-78      
Au-197  ENDF/B-VI 7.0   H-H2O   ENDF/B-VI 7.0   S-32    JENDL 3.3    
B-10    ENDF/B-VI 7.0   He-3    ENDF/B-VI 7.0   S-33    JENDL 3.3    
B-11    ENDF/B-VI 7.0   He-4    ENDL-78         S-34    JENDL 3.3    
Ba-130  ENDF/B-VI 7.0   Hf-174  JENDL 3.3       S-36    JENDL 3.3    
Ba-132  ENDF/B-VI 7.0   Hf-176  JENDL 3.3       S-nat   JENDL 3.2    
Ba-134  ENDF/B-VI 7.0   Hf-177  JENDL 3.3       Sb-121  ENDF/B-VI 7.0
Ba-135  ENDF/B-VI 7.0   Hf-178  JENDL 3.3       Sb-123  ENDF/B-VI 7.0
Ba-136  ENDF/B-VI 7.0   Hf-179  JENDL 3.3       Sb-nat  JENDL 3.2    
Ba-137  ENDF/B-VI 7.0   Hf-180  JENDL 3.3       Sc-45   ENDF/B-VI 7.0
Ba-138  ENDF/B-VI 7.0   Hg-196  ENDF/B-VI 7.0   Si-28   ENDF/B-VI 6.8
Be-9    ENDF/B-VI 6.8   Hg-198  ENDF/B-VI 7.0   Si-29   ENDF/B-VI 6.8
Bi-209  ENDF/B-VI 6.8   Hg-199  ENDF/B-VI 7.0   Si-30   ENDF/B-VI 6.8
Br-79   ENDF/B-VI 7.0   Hg-200  ENDF/B-VI 7.0   Sm-144  ENDF/B-VI 7.0
Br-81   ENDF/B-VI 7.0   Hg-201  ENDF/B-VI 7.0   Sm-147  ENDF/B-VI 7.0
C-Gra   ENDF/B-VI 7.0   Hg-202  ENDF/B-VI 7.0   Sm-148  ENDF/B-VI 7.0
C-nat   ENDF/B-VI 7.0   Hg-204  ENDF/B-VI 7.0   Sm-149  ENDF/B-VI 7.0
Ca-40   ENDF/B-VI 7.0   I-127   ENDF/B-VI 7.0   Sm-150  ENDF/B-VI 7.0
Ca-42   ENDF/B-VI 7.0   I-129   ENDF/B-VI 7.0   Sm-152  ENDF/B-VI 7.0
Ca-43   ENDF/B-VI 7.0   In-113  ENDF/B-VI 7.0   Sm-154  ENDF/B-VI 7.0
Ca-44   ENDF/B-VI 7.0   In-115  ENDF/B-VI 7.0   Sn-112  ENDF/B-VI 6.8
Ca-46   ENDF/B-VI 7.0   In-nat  ENDF/B-VI 6.8   Sn-114  ENDF/B-VI 6.8
Ca-48   ENDF/B-VI 7.0   K-39    ENDF/B-VI 7.0   Sn-115  ENDF/B-VI 6.8
Ca-nat  ENDF/B-VI 7.0   K-40    ENDF/B-VI 7.0   Sn-116  ENDF/B-VI 6.8
Cd-106  JENDL 3.3       K-41    ENDF/B-VI 7.0   Sn-117  ENDF/B-VI 6.8
Cd-108  JENDL 3.3       K-nat   ENDF/B-VI 6.8   Sn-118  ENDF/B-VI 6.8
Cd-110  JENDL 3.3       Kr-78   ENDF/B-VI 6.8   Sn-119  ENDF/B-VI 6.8
Cd-111  JENDL 3.3       Kr-80   ENDF/B-VI 6.8   Sn-120  ENDF/B-VI 6.8
Cd-112  JENDL 3.3       Kr-82   ENDF/B-VI 6.8   Sn-122  ENDF/B-VI 6.8
Cd-113  JENDL 3.3       Kr-83   ENDF/B-VI 6.8   Sn-124  ENDF/B-VI 6.8
Cd-114  JENDL 3.3       Kr-84   ENDF/B-VI 6.8   Sr-90   ENDF/B-VI 6.8
Cd-115  ENDF/B-VI 7.0   Kr-86   ENDF/B-VI 6.8   Ta-181  JENDL 3.3    
Cd-116  JENDL 3.3       Li-6    JENDL 3.3       Tc-99   ENDF/B-VI 7.0
Ce-136  ENDF/B-VI 7.0   Li-7    JENDL 3.3       Th-230  ENDF/B-VI 6.8
Ce-138  ENDF/B-VI 7.0   Mg-24   JENDL 3.3       Th-232  ENDF/B-VI 6.8
Ce-140  ENDF/B-VI 7.0   Mg-25   JENDL 3.3       Ti-46   JENDL 3.3    
Ce-142  ENDF/B-VI 7.0   Mg-26   JENDL 3.3       Ti-47   JENDL 3.3    
Cl-35   ENDF/B-VI 7.0   Mg-nat  ENDF/B-VI 6.8   Ti-48   JENDL 3.3    
Cl-37   ENDF/B-VI 7.0   Mn-55   ENDF/B-VI 6.8   Ti-49   JENDL 3.3    
Cl-nat  ENDF/B-VI 7.0   Mo-100  EFF 2.4         Ti-50   JENDL 3.3    
Co-59   ENDF/B-VI 7.0   Mo-92   EFF 2.4         Ti-nat  ENDF/B-VI 6.8
Cr-50   ENDF/B-VI 6.8   Mo-94   EFF 2.4         U-234   ENDL-78      
Cr-52   ENDF/B-VI 6.8   Mo-95   EFF 2.4         U-235   ENDF/B-VI 6.8
Cr-53   ENDF/B-VI 6.8   Mo-96   EFF 2.4         U-238   ENDF/B-VI 6.8
Cr-54   ENDF/B-VI 6.8   Mo-97   EFF 2.4         V-nat   JENDL 3.3    
Cs-133  ENDF/B-VI 7.0   Mo-98   EFF 2.4         W-182   ENDF/B-VI 7.0
Cs-135  ENDF/B-VI 7.0   N-14    ENDF/B-VI 7.0   W-183   ENDF/B-VI 7.0
Cs-137  ENDF/B-VI 7.0   N-15    JENDL 3.3       W-184   ENDF/B-VI 7.0
Cu-63   ENDF/B-VI 6.8   Na-23   JENDL 3.3       W-186   ENDF/B-VI 7.0
Cu-65   ENDF/B-VI 6.8   Nb-93   ENDF/B-VI 6.8   Xe-124  ENDF/B-VI 7.0
D-D2O   ENDF/B-VI 7.0   Nd-142  ENDF/B-VI 7.0   Xe-126  ENDF/B-VI 7.0
Eu-151  ENDF/B-VI 6.8   Nd-143  ENDF/B-VI 7.0   Xe-128  ENDF/B-VI 7.0
Eu-153  ENDF/B-VI 6.8   Nd-144  ENDF/B-VI 7.0   Xe-129  ENDF/B-VI 7.0
F-19    ENDF/B-VI 6.8   Nd-145  ENDF/B-VI 7.0   Xe-130  ENDF/B-VI 7.0
Fe-54   ENDF/B-VI 6.8   Nd-146  ENDF/B-VI 7.0   Xe-131  ENDF/B-VI 7.0
Fe-56   ENDF/B-VI 6.8   Nd-148  ENDF/B-VI 7.0   Xe-132  ENDF/B-VI 7.0
Fe-57   ENDF/B-VI 6.8   Nd-150  ENDF/B-VI 7.0   Xe-134  ENDF/B-VI 7.0
Fe-58   ENDF/B-VI 6.8   Ni-58   ENDF/B-VI 6.8   Xe-135  ENDF/B-VI 7.0
Ga-69   ENDF/B-VI 7.0   Ni-60   ENDF/B-VI 6.8   Xe-136  ENDF/B-VI 7.0
Ga-71   ENDF/B-VI 7.0   Ni-61   ENDF/B-VI 6.8   Y-89    ENDF/B-VI 6.8
Ga-nat  JEFF 3.1        Ni-62   ENDF/B-VI 6.8   Zn-nat  JEFF 3.0     
Gd-152  ENDF/B-VI 7.0   Ni-64   ENDF/B-VI 6.8   Zr-90   ENDF/B-VI 7.0
Gd-154  ENDF/B-VI 7.0   O-16    ENDF/B-VI 6.8   Zr-91   ENDF/B-VI 7.0
Gd-155  ENDF/B-VI 7.0   O-17    ENDF/B-VI 7.0   Zr-92   ENDF/B-VI 7.0
Gd-156  ENDF/B-VI 7.0   P-31    JENDL 3.3       Zr-94   ENDF/B-VI 7.0
Gd-157  ENDF/B-VI 7.0   Pb-204  ENDF/B-VI 7.0   Zr-96   ENDF/B-VI 7.0
Gd-158  ENDF/B-VI 7.0   Pb-206  ENDF/B-VI 6.8   Zr-nat  ENDL-78      
Gd-160  ENDF/B-VI 7.0   Pb-207  ENDF/B-VI 6.8
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  No gamma interaction data are given.
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7. UNUSUAL FEATURES

Neutron to charged particle scattering matrices are included.
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8. RELATED OR AUXILIARY PROGRAMS:  NJOY 99.259, FLUKA.
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9. STATUS
Package ID Status date Status
NEA-1822/01 01-OCT-2008 Tested at NEADB
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10. REFERENCES
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11. HARDWARE REQUIREMENTS

The disk space required for loading the libraries is about 3.54 Gb.
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

  Alfredo Ferrari
  Dana Ene
  Alberto Fasso'
  Florian Sommerer
  CERN - AB Department
  Blg. 864-2-D05
  Mail Box Z03000
  CH-1211 Geneve 23
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16. MATERIAL AVAILABLE
NEA-1822/01
files for each material in gendf format
neutron to charged particle scattering matrices at infinite dilution
neutron interaction data libray
neutron to gamma ray matrices
   files for each material in dtf format
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17. CATEGORIES
  • Z. Data.

Keywords: charged particles, cross sections, gas production, kerma factors, multigroup, neutron, photon.