RSICC Home Page VITJEF22.BOLIB

RSICC DATA PACKAGE DLC-241

1.         NAME AND TITLE OF DATA LIBRARY

VITJEF22.BOLIB:          JEF-2.2 Multigroup Coupled (199n + 42γ) Cross-Section Library in AMPX Format for Nuclear Fission Applications

2.         NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

AIM: Convert AMPX master card-image data to binary format. AIM is not included but is distributed in AMPX, SCALE and SCAMPI packages.

3.         CONTRIBUTOR

ENEA, Italian National Agency for New Technologies, Energy and the Environment, 'E. Clementel' Research Centre, Bologna, Italy, and Institute of Physics and Power Engineering, Obninsk, Russian Federation, through the OECD Nuclear Energy Agency Data Bank, Issy-les Moulineaux, France.

4.         HISTORICAL BACKGROUND AND INFORMATION

The ENEA-Bologna Nuclear Data Centre produced the VITJEF22.BOLIB library within the framework of co-operation with specialists of the Obninsk Institute of Physics and Power Engineering (IPPE-Obninsk, Russian Federation). The VITJEF22.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 general features as VITAMIN-B6 and was produced using the same data processing methodologies, based on the NJOY-94.66 and SCAMPI data processing systems.

5.         APPLICATION OF THE DATA

From VITJEF22.BOLIB it is possible to easily generate, through further data processing with the AMPX or SCAMPI systems, working libraries of self-shielded cross sections in AMPX or FIDO-ANISN format to be used in transport calculations with the AMPX, SCAMPI, SCALE, DOORS, DANTSYS, and MORSE systems.

6.         SOURCE AND SCOPE OF DATA

ORIGINAL NUCLEAR DATA FILE: JEF-2.2

DATA PROCESSING SYSTEMS: NJOY-94.66 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 NUMBER OF MATERIALS: 138

MATERIALS INCLUDED: one file per material (nat=natural):

 

H-H2O

H-CH2

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 prompt 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.

VITJEF22.BOLIB was extensively tested on many thermal and fast criticality benchmark experiments.

7.         DISCUSSION OF THE DATA RETRIEVAL PROGRAM

VITJEF22.BOLIB in AMPX format (NEA-1699/01) and MATJEF22.BOLIB in MATXS format (NEA-1740/01) are twin libraries produced in ENEA-Bologna and derived from the same set of cross section files in GENDF format, obtained from NJOY-94.66.

VITJEF22.BOLIB is a pseudo-problem-independent library based on the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 133 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 JEF-2.2 thermal scattering law data file for 5 additional bound nuclides (H-1 in light water (H-H2O), H-1 in polyethylene (H-CH2), H-2 in heavy water (H2-D2O), C in graphite (C-GPH) and Be in beryllium metal (Be-TH)).

8.         DATA FORMAT AND COMPUTER

(RSICC ID: D00241MNYCP00, NEA-1699/01)

9.         TYPICAL RUNNING TIME

Not applicable.

10.        REFERENCES

a.   Documentation available with library

M. Pescarini, et al., 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.

b.   Other useful documentation

N. M. Greene, W. E. Ford III, L. M. Petrie, and 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.

The JEF-2.2 Nuclear Data Library, JEFF Report 17, OECD/NEA Data Bank, April 2000.

R. E. MacFarlane and D. W. Muir, The NJOY Nuclear Data Processing System, Version 94.66, Los Alamos National Laboratory, December 19, 1996.

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.

J. E. White, et al., 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, ORNL-6795/R1, 2000.

M. Pescarini, et al., MATJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199n + 42 gamma) Cross Section Library in MATXS Format for Nuclear Fission Applications, ENEA Internal Report FIS-P815-007, June 6, 2004.

I. I. Bondarenko, M. N. Nikolaev, L. P. Abagyan, and N. O. Bazaziants, “Group Constants for Nuclear Reactors Calculations,” translated into English by Consultants Bureau, New York, 1964.

11.        CONTENTS OF LIBRARY

The package is transmitted on a CD which contains the reports listed in section 10.a above, the data files, and test cases.

12.        DATE OF ABSTRACT

August 2010

Keywords:              CROSS SECTIONS, DATA LIBRARY, EVALUATED DATA, MULTIGROUP