RSICC Home Page VITJEFF31.BOLIB

RSICC DATA PACKAGE DLC-235

1.         NAME AND TITLE OF DATA LIBRARY

VITJEFF31.BOLIB         Multigroup Coupled (199n + 42gamma) X-Section Lib. in AMPX Format for Nuclear Fission Applications.

2.         NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

ENEA-Bologna Revised Versions of NJOY-99.160 and SCAMPI.

3.         CONTRIBUTOR

ENEA Italian National Agency for New Technologies, Energy and the Environment, Bologna, Italy, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Moulineaux, France.

4.         HISTORICAL BACKGROUND AND INFORMATION

The ENEA-Bologna Nuclear Data Group produced the VITJEFF31.BOLIB library in cooperation with a 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 the 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.

5.         APPLICATION OF THE DATA

VITJEFF31.BOLIB is a multigroup coupled library (199 neutron groups and 42 photon groups) pseudo-problem independent cross section library in AMPX format for nuclear fission applications. VITJEFF31.BOLIB is based on the JEFF-3.1 OECD/NEA Data Bank nuclear data library and it was processed, through the NJOY-99.160 system with an ENEA-Bologna revised GROUPR module and the ENEA-Bologna 2007 Revision of the SCAMPI system, in the VITAMIN-B6 energy group structure using the same parameters and calculation procedures.

6.         SOURCE AND SCOPE OF DATA

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.

7.         DISCUSSION OF THE DATA RETRIEVAL PROGRAM

The VITJEFF31.BOLIB is 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.

8.         DATA FORMAT AND COMPUTER

ASCII; CPU INTEL X86

9.         TYPICAL RUNNING TIME

None noted.

10.        REFERENCES

a.         Documentation

M. Pescarini, V. Sinitsa, and 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.

b.         Other useful documentation

M. Pescarini, V. Sinitsa, and R. Orsi, “ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications,” in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, editors O. Bersillon, F. Gunsing, E. Bauge, R. Jacqmin, and S. Leray, EDP Sciences, 2008, pp 705708.

A. Koning et al, “The JEFF Evaluated Nuclear Data Project,” in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, editors O. Bersillon, F. Gunsing, E. Bauge, R. Jacqmin, and S. Leray, EDP Sciences, 2008, pp 721726.  

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, Oak Ridge National Laboratory, October 1992. Also available from OECD/NEA Data Bank as PSR-0315 AMPX-77.

V. Sinitsa, Private Communication, Activity Report of ENEA Research Fellowship, May 31, 2006.

V. Sinitsa, and M. Pescarini, ENEA-Bologna 2007 Revision of the SCAMPI (ORNL) Nuclear Data Processing System, ENEA Internal Report FPN-P9H6-006, September 13, 2007.

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, 1996. Also available from OECD/NEA Data Bank as DLC-0184 ZZ-VITAMIN-B6.

M. Pescarini et al., VITJEF22.BOLIB - A JEF-2.2 Multigroup Coupled (199n + 42 gamma) Cross Section Library AMPX Format for Nuclear Fission Applications, ENEA Internal Report FIS-P815-001, April 16, 2003.

I. I. Bondarenko, M. N. Nikolaev, L. P. Abagyan, and N. O. Bazaziants, Group Constants for Nuclear Reactors Calculations, published by Consultants Bureau, New York1964.

SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section Libraries in AMPX Format, Oak Ridge National Laboratory, RSICC Peripheral Shielding Routine Collection PSR-352, September 1995. Available from OECD/NEA Data Bank as PSR-0352 SCAMPI.

11.        CONTENTS OF LIBRARY

This package contains the documentation for the VITJEFF31.BOLIB data library, ASCII library files and a README file. Files are transmitted on one CD in a compressed file format.

12.        DATE OF ABSTRACT

January 2010.

KEYWORDS:        AMPX INTERFACE FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS