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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-BUGENDF70.BOLIB | NEA-1872/01 | Tested | 11-FEB-2013 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1872/01 | Linux-based PC | Linux-based PC |
The ENEA-Bologna Nuclear Data Group generated the BUGENDF70.BOLIB /1/ library in FIDO-ANISN format. BUGENDF70.BOLIB is a broad-group coupled neutron and photon working cross section library, dedicated to LWR shielding and pressure vessel dosimetry applications and it is based on the US ENDF/B-VII.0 /2/ library of evaluated nuclear data. The neutron and photon energy group structures (47 neutron groups + 20 photon groups) of BUGENDF70.BOLIB are the same as those of the corresponding BUGLE-96 /3/ similar library generated at ORNL in 1996, based on the US ENDF/B-VI.3 evaluated nuclear data. BUGENDF70.BOLIB was produced from the ENEA-Bologna VITENDF70.BOLIB /4/ 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 /5/ of the SCAMPI /6/ nuclear data processing system, using neutron and photon flux spectra typical of PWR and BWR reactor models. BUGENDF70.BOLIB, differently from BUGLE-96 which contains only prompt neutron fission spectra and prompt neutrons per fission data, includes total (prompt + delayed) neutron fission spectra for 34 fissionable nuclides (Am-242 not included because MF=4 MT=18 missing in the evaluated data) and total (prompt + delayed) neutrons per fission for 35 fissionable nuclides. The ENEA-Bologna VITENDF70.BOLIB and BUGENDF70.BOLIB libraries, based on US ENDF/B-VII.0 data, have similar counterparts respectively in the VITJEFF311.BOLIB /7/ and BUGJEFF311.BOLIB /8/ libraries, based on OECD-NEADB JEFF-3.1.1 /9/ /10/ data.
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 183 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: ENDF/B-VII.0
DATA PROCESSING SYSTEMS: ENEA-Bologna 2007 Revision of SCAMPI
FORMAT: FIDO-ANISN
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
MATERIALS INCLUDED:
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 |
|
nat=natural element
Gph=graphite
Th=thermal
D=H2=deuterium
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:
off-center in a BWR core region;
off-center in a PWR core region;
within the downcomer region in a PWR model;
within the PWR pressure vessel (PV) at a depth of one-fourth the total thickness (T) (1/4 T PV);
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 various material mixtures, typical of BWR and PWR compositional models, were produced with the neutron and photon flux spectra calculated in the cited spatial locations.
RESPONSE FUNCTIONS
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.
The BUGENDF70.BOLIB library was generated, through cross section collapsing of the ENEA-Bologna VITENDF70.BOLIB /4/ fine-group general-purpose library for nuclear fission applications, using the updated and corrected ENEA-Bologna 2007 Revision /5/ of the ORNL SCAMPI /6/ nuclear data processing system. In particular this ENEA-Bologna version of the SCAMPI system, already transferred to OECD-NEA Data Bank (PSR-0352/05 SCAMPI), permits to obtain the total (prompt + delayed) neutron fission spectra and the total (prompt + delayed) neutrons per fission data of the fissionable nuclides, differently from the original version of SCAMPI developed at ORNL.
The adopted cross section processing methodology for BUGENDF70.BOLIB is the same as that used for producing the BUGLE-96 library and is consistent with the ANSI/ANS 6.1.2-1999 (R2009) /11/ American National Standard, reapproved in 2009.
The VITENDF70.BOLIB cross sections were generated with the LANL NJOY-99.259 data processing system and were converted into the AMPX format using the SMILER module of the previously cited ENEA-Bologna 2007 Revision of the SCAMPI system. VITENDF70.BOLIB is a pseudo-problem-independent library based on the Bondarenko /12/ (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. It has the same neutron and photon energy group structures (199 neutron groups + 42 photon groups) as the ORNL VITAMIN-B6 /3/ library in AMPX format (based on the ENDF/B-VI.3 evaluated nuclear data) from which the BUGLE-96 library was generated at ORNL.
The VITENDF70.BOLIB library contains 183 nuclides: 177 nuclides at 4 temperatures, most of them obtained with 6 to 8 values of the background cross section. The Fe-56 processed file was obtained with an additional value (0.01 barns) for the background cross section with respect to the background cross section values used to generate the corresponding data file for VITAMIN-B6.
Thermal scattering cross sections were processed at all the temperatures available in the ENDF/B-VII.0 thermal scattering law data file for 6 additional bound nuclides: (H-1 in light water (H-H2O), H-1 in polyethylene (H-CH2), H-1 in zirconium hydride (H-ZrH), H-2 deuterium (D) in heavy water (D-D2O), C in graphite (C-Gph) and Be in beryllium metal thermal (Be-Th)).
From VITENDF70.BOLIB it is possible to generate easily, through further proper data processing, working libraries of collapsed and self-shielded cross sections in AMPX format for calculations with the AMPX, SCAMPI and SCALE systems or in FIDO-ANISN format (as for example the BUGENDF70.BOLIB library) for calculations with the DOORS and PARTISN deterministic transport systems and finally for calculations with the MORSE Monte Carlo code.
This problem-dependent data processing must be exclusively performed through the ENEA-Bologna 2007 Revision of the SCAMPI system that can read the binary files generated by NJOY-99 with double precision data.
References cited in the present text:
/1/ 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.
/2/ 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.
/3/ 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.
/4/ 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.
/5/ 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.
The ENEA-Bologna 2007 Revision of the SCAMPI system is available
from the OECD-NEA Data Bank as PSR-0352/05 SCAMPI.
/6/ 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.
/7/ 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.
/8/ 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.
/9/ The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD-NEA Data Bank,
2009.
/10/ The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD-NEA Data Bank,
2006.
/11/ 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).
/12/ I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, Group
Constants for Nuclear Reactors Calculations, Consultants Bureau,
New York, 1964.
/13/ 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.
The ADEFTA-4.1 code is available at the OECD-NEA Data Bank
as NEA-1708 ADEFTA-4.1.
The present package requires about 109 MBytes of diskspace.
Tested on:
COMPUTER : P.C. (CPU INTEL Pentium III, 448MB of RAM).
OPERATING SYSTEM : Red Hat Linux 7.1.
COMPUTER : P.C. (CPU INTEL(R) Pentium(R) D CPU 3.40 GHz, 3.10 GB of RAM).
OPERATING SYSTEM : Linux openSUSE 10.2 (i586).
Massimo PESCARINI
ENEA
Italian National Agency for New Technologies, Energy and the Environment
"E. Clementel" Research Centre
Bologna - Italy
Valentin SINITSA
ENEA consultant
formerly at IPPE
Institute of Physics and Power Engineering
Obninsk, Russian Federation.
Roberto ORSI
ENEA
Italian National Agency for New Technologies, Energy and the Environment
"E. Clementel" Research Centre
Bologna - Italy
Manuela FRISONI
ENEA
Italian National Agency for New Technologies, Energy and the Environment
"E. Clementel" Research Centre
Bologna - Italy
Keywords: LWR reactors, data library, multigroup, pressure vessels, pwr reactors, self-shielding, shielding.
