BUGENDF70.BOLIB - ENDF/B-VII.0 Broad-Group Coupled Cross Section Library for LWR Shielding & Pressure Vessel Dosimetry Applications.
ENEA-Bologna 2007 Revision of SCAMPI.
ENEA-Bologna Nuclear Data Group, Bologna, Italy through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.
The BUGENDF70.BOLIB library package
consists of two major parts:
BUGENDF70.BOLIB - Version without upscattering cross sections including an infinite dilution cross section set for 183 nuclides and six sets of parameterized self-shielded cross sections containing a total of 124 nuclides. Each set of parameterized cross sections includes part of the 83 nuclides previously cited and the cross sections contained are properly self-shielded, i.e., take into account the specific temperature and background cross section of the specific nuclide constituent of a typical BWR or PWR material mixture.
BUGENDF70T.BOLIB - Version with upscattering cross sections including the same cross section sets as BUGENDF70.BOLIB with the thermal neutron upscattering cross sections retained in the thermal neutron energy region below 5.0435 eV: upscatter data for four thermal neutron groups are included. The upscatter data should improve the application of this library to the calculation of more accurate thermal fluences, although more computer time will be required.
A preliminary testing of the BUGENDF70.BOLIB library was performed through three-dimensional fixed source transport calculations with the TORT-3.2 discrete ordinates (SN) code on the PCA-Replica 12/13 and VENUS-3 engineering neutron shielding benchmark experiments, included in the SINBAD international database of fission reactor shielding integral experiments. The two cited experiments were specifically conceived to check the nuclear data and transport codes used in LWR radiation shielding and radiation damage analyses.
ORIGINAL NUCLEAR DATA FILE:
DATA PROCESSING SYSTEMS: ENEA-Bologna 2007 Revision of SCAMPI
NUMBER OF GROUPS: 47 neutron groups and 20 photon groups
THERMAL NEUTRON GROUPS: 5 neutron groups below 5.043 eV without/with upscattering cross sections retained
NEUTRON ENERGY RANGE: 1.0E-5 eV - 17.332 MeV
PHOTON ENERGY RANGE: 10.0 keV - 14.0 MeV
CROSS SECTION LEGENDRE ORDER: P7 for materials with Z less or equal to 29 (copper); P5 for the remainder of the nuclides
NUMBER OF MATERIALS: 183
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-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-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 AND PHOTON WEIGHTING SPECTRA:
Five fine-group (199 neutron groups + 42 photon groups) neutron and photon problem-dependent weighting spectra were employed to generate the BUGENDF70.BOLIB cross sections through VITENDF70.BOLIB cross section collapsing. These problem-dependent weighting spectra were pre-calculated with the XSDRNPM one-dimensional transport module of the ENEA-Bologna 2007 Revision of the ORNL SCAMPI system. The calculations were performed in representative spatial locations of the radial geometries of the BWR and PWR one-dimensional models. In particular neutron and photon flux spectra calculated in the following five specific locations were used to obtain the collapsed cross section sets:
1) off-center in a BWR core region;
2) off-center in a PWR core region;
3) within the downcomer region in a PWR model;
4) within the PWR pressure vessel (PV) at a depth of one-fourth the total thickness (T) (1/4 T PV);
5) within the concrete shield surrounding a PWR pressure vessel.
In particular an infinite dilution cross section set containing 183 materials was generated through cross section collapsing using the neutron and photon flux spectra calculated within the concrete shield surrounding a PWR reactor pressure vessel. The concrete-spectrum-weighted cross sections have been shown to be generally applicable to a wide range of shielding problems. In addition, six parameterized cross section sets of self-shielded cross sections for variuos material mixtures, typical of BWR and PWR compositional models, were produced with the neutron and photon flux spectra calculated in the cited spatial locations.
The BUGENDF70.BOLIB library contains several types of response functions.
"General Neutron Response Functions"
This set of data includes the neutron group upper energies, the group energy widths, the group lethargy widths, the group midpoint energies (E-mid), the group square-roots of E-mid and the group multiplicative factors for the total neutron flux, the E>1.0 MeV neutron flux, the E>0.1 MeV neutron flux and the E<0.414 eV neutron flux.
"Total Neutron Fission Spectra (chi) and Total Neutrons per Fission (nu)"
This set of data includes the total (prompt + delayed) neutron fission spectra (chi) for 34 fissionable nuclides (Am-242 not included because MF=4 MT=18 missing in the evaluated data) and the total (prompt + delayed) neutrons per fission (nu) for 35 fissionable nuclides. The total neutrons per fission were obtained with two different weighting spectra: flat weighting and 1/4 T PV weighting.
"IAEA IRDF-2002 Neutron Dosimeter Cross Sections"
This set of data contains the dosimeter cross sections for all the 71 nuclear reactions included in the IAEA IRDF-2002 International Reactor Dosimetry File. The IRDF-2002 neutron dosimeter cross sections were processed in the 47 neutron group structure of BUGENDF70.BOLIB with two different neutron weighting spectra: flat weighting and 1/4 T PV weighting.
"Neutron and Photon KERMA Factors"
This set of data includes the neutron KERMA factors for all the 183 materials contained in the infinite dilution cross section set of BUGENDF70.BOLIB and the photon KERMA factors are given for the corresponding 53 natural elements. The collapsing of the neutron and photon KERMA factors was obtained by using respectively the neutron and photon flux spectra calculated within the concrete shield surrounding a PWR pressure vessel.
BUGENDF70.BOLIB was produced from the ENEA-Bologna VITENDF70.BOLIB fine-group mother library in AMPX format, based on ENDF/B-VII.0 data. The fine-group data of VITENDF70.BOLIB were collapsed and in some cases shelf-shielded, through the ENEA-Bologna 2007 Revision of the SCAMPI nuclear data processing system, using neutron and photon flux spectra typical of PWR and BWR reactor models.
PC Windows and Linux (D00262PCX8600). The present package requires about 109 MBytes of diskspace.
a. Included Documentation.
M. Pescarini, V. Sinitsa, R. Orsi, M. Frisoni, “BUGENDF70.BOLIB – An ENDF/B-VII.0 Broad-Group Coupled (47 n + 20 gamma) Cross Section Library in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications”, ENEA-Bologna Technical Report UTFISSM-P9H6-008 (January 10, 2013).
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).
R. Orsi, “ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis”, ENEA-Bologna Technical Report FPN-P9H6-010 (May 20, 2008).
b. Background References.
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).
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).
M. Pescarini, V. Sinitsa, R. Orsi, M. Frisoni, “VITENDF70.BOLIB – An ENDF/B-VII.0 Multi-Group Coupled (199 n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications”, ENEA-Bologna Technical Report UTFISSM-P9H6-005 (May 25, 2012).
“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).
M. Pescarini, V. Sinitsa, R. Orsi, “VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications”, ENEA-Bologna Technical Report UTFISSM-P9H6-003 (November 10, 2011).
M. Pescarini, V. Sinitsa, R. Orsi, M. Frisoni, “BUGJEFF311.BOLIB – A JEFF-3.1.1 Broad-Group Coupled (47 n + 20 gamma) Cross Section Library in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications”, ENEA-Bologna Technical Report UTFISSM-P9H6-002 (May 12, 2011).
“The JEFF-3.1.1 Nuclear Data Library”, JEFF Report 22, OECD-NEA Data Bank (2009).
“The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD-NEA Data Bank (2006).
“American National Standard, American Nuclear Society, Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants”, ANSI/ANS-6.1.2-1999 (R2009).
I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, “Group Constants for Nuclear Reactors Calculations”, Consultants Bureau, New York (1964).
11. CONTENTS OF LIBRARY
The BUGENDF70.BOLIB package is transmitted on CD and includes the data files along with the references listed in Section 10(a).
KEYWORDS: LWR REACTORS, DATA LIBRARY, MULTIGROUP, PRESSURE VESSELS, PWR REACTORS, SELF-SHIELDING, SHIELDING