FLUKA05-PRE-LIB

RSICC DATA PACKAGE DLC-260

1. NAME AND TITLE OF DATA LIBRARY

FLUKA05-PRE-LIB: FLUKA05 Multi-Group, Multi-Purpose Nuclear Data Library, Neutrons, Photons, Charged Particles.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

NJOY-99 (P00480MNYCP00)

FLUKA (NEA-1833/07).

3. CONTRIBUTOR

AB Department, European Organization for Nuclear Research (CERN), Geneva, Switzerland through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.

4. HISTORICAL BACKGROUND AND INFORMATION

During the preparation of the FLUKA05 Multi-group Nuclear Data Library, 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.

5. APPLICATION OF THE DATA

The main features of the library include:
- Source of the data: many;
- 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;
- 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 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.

6. SOURCE AND SCOPE OF DATA

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

No gamma interaction data are given.

Neutron to charged particle scattering matrices are included.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

All the computations have been carried out by NJOY 99.259 with some minor modifications to speed up the handling of the data.

8. DATA FORMAT AND COMPUTER

PC Windows and Linux (D00260PCX8600).

9. TYPICAL RUNNING TIME

N/A

10. REFERENCES

a. Documentation available with library

“Readme.nea” (October 3, 2008).

11. CONTENTS OF LIBRARY

The FLUKA05-PRE-LIB package is transmitted on CD and includes the referenced document along with data files written in both GENDF format and DTF format.

12. DATE OF ABSTRACT

September 2012.

KEYWORDS: CHARGED PARTICLES, CROSS SECTIONS, GAS PRODUCTION, KERMA FACTORS, MULTIGROUP, NEUTRON, PHOTON