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:
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:

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.

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.

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).

April 2013.

**KEYWORDS:** LWR REACTORS,
DATA LIBRARY, MULTIGROUP, PRESSURE VESSELS, PWR REACTORS, SELF-SHIELDING,
SHIELDING