Program name  Package id  Status  Status date 

ZZBUGJEFF311.BOLIB  NEA1866/02  Tested  03APR2013 
Machines used:
Package ID  Orig. computer  Test computer 

NEA1866/02  Many Computers  Linuxbased PC 
The ENEABologna Nuclear Data Group generated the BUGJEFF311.BOLIB /1/ library in FIDOANISN format. BUGJEFF311.BOLIB is a broadgroup coupled neutron and photon working cross section library dedicated to LWR shielding and pressure vessel dosimetry applications and it is based on the OECDNEA Data Bank JEFF3.1.1 /2//3/ library of evaluated nuclear data. The neutron and photon energy group structures (47 neutron groups + 20 photon groups) of BUGJEFF311.BOLIB are the same as those of the corresponding BUGLE96 /4/ similar library generated at ORNL in 1996, based on ENDF/BVI.3 evaluated nuclear data. BUGJEFF311.BOLIB was produced from the ENEABologna VITJEFF311.BOLIB /5/ finegroup mother library in AMPX format, based on JEFF3.1.1 data.
The finegroup data of VITJEFF311.BOLIB were collapsed and in some cases selfshielded, through the ENEABologna 2007 Revision /6/ of the SCAMPI /7/ nuclear data processing system, using neutron and photon flux spectra typical of PWR and BWR reactor models. The ENEABOLOGNA VITJEFF311.BOLIB and BUGJEFF311.BOLIB libraries can be respectively considered as European counterparts of the ORNL VITAMINB6 /4/ and BUGLE96 libraries. BUGJEFF311.BOLIB, differently from BUGLE96 which contains only prompt neutron fission spectra (chi) and prompt neutrons per fission (nu) data, includes total (prompt + delayed) neutron fission spectra and total (prompt + delayed) neutrons per fission for 35 fissionable nuclides.
The BUGJEFF311.BOLIB library package consists of two major parts:
BUGJEFF311.BOLIB  Version without upscattering cross sections including an infinite dilution
cross section set for 182 nuclides and six sets of parameterized
selfshielded cross sections containing a total of 124 nuclides.
Each set of parameterized cross sections includes part of the 182 nuclides
previously cited and the cross sections contained are properly selfshielded, 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.
BUGJEFF311T.BOLIB  Version with upscattering cross sections including the same cross section sets
as BUGJEFF311.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 BUGJEFF311.BOLIB library was performed through threedimensional fixed source transport calculations with the TORT3.2 discrete ordinates (SN) code on the PCAReplica 12/13 and VENUS3 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: JEFF3.1.1
DATA PROCESSING SYSTEMS: ENEABologna 2007 Revision of SCAMPI
FORMAT: FIDOANISN
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: 1.0E5 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: 182
MATERIALS INCLUDED:
HH2O  HCH2  HZrH  DD2O  H3  He3  He4  Li6 
Li7  Be9  BeTh  B10  B11  Cnat  CGph  N14 
N15  O16  O17  F19  Na23  Mg24  Mg25  Mg26 
Al27  Si28  Si29  Si30  P31  S32  S33  S34 
S36  Cl35  Cl37  K39  K40  K41  Ca40  Ca42 
Ca43  Ca44  Ca46  Ca48  Ti46  Ti47  Ti48  Ti49 
Ti50  Vnat  Cr50  Cr52  Cr53  Cr54  Mn55  Fe54 
Fe56  Fe57  Fe58  Co59  Ni58  Ni60  Ni61  Ni62 
Ni64  Cu63  Cu65  Ganat  Y89  Zr90  Zr91  Zr92 
Zr94  Zr96  Nb93  Mo92  Mo94  Mo95  Mo96  Mo97 
Mo98  Mo100  Ag107  Ag109  Cd106  Cd108  Cd110  Cd111 
Cd112  Cd113  Cd114  Cd115m  Cd116  In113  In115  Sn112 
Sn114  Sn115  Sn116  Sn117  Sn118  Sn119  Sn120  Sn122 
Sn123  Sn124  Sn125  Sn126  Ba138  Eu151  Eu152  Eu153 
Eu154  Eu155  Gd152  Gd154  Gd155  Gd156  Gd157  Gd158 
Gd160  Er162  Er164  Er166  Er167  Er168  Er170  Hf174 
Hf176  Hf177  Hf178  Hf179  Hf180  Ta181  Ta182  W182 
W183  W184  W186  Re185  Re187  Au197  Pb204  Pb206 
Pb207  Pb208  Bi209  Th230  Th232  Pa231  Pa233  U232 
U233  U234  U235  U236  U237  U238  Np237  Np238 
Np239  Pu236  Pu237  Pu238  Pu239  Pu240  Pu241  Pu242 
Pu243  Pu244  Am241  Am242  Am242m  Am243  Cm241  Cm242 
Cm243  Cm244  Cm245  Cm246  Cm247  Cm248 


nat=natural element
Gph=graphite
Th=thermal
D=H2=deuterium
NEUTRON AND PHOTON WEIGHTING SPECTRA:
Five finegroup (199 neutron groups + 42 photon groups) neutron and photon problemdependent weighting spectra were employed to generate the BUGJEFF311.BOLIB cross sections through VITJEFF311.BOLIB cross section collapsing. These problemdependent weighting spectra were precalculated with the XSDRNPM onedimensional transport module of the ENEABOLOGNA 2007 Revision of the ORNL SCAMPI system. The calculations were performed in representative spatial locations of the radial geometries of the BWR and PWR onedimensional models. In particular neutron and photon flux spectra calculated in the following five specific locations were used to obtain the collapsed cross section sets:
offcenter in a BWR core region;
offcenter in a PWR core region;
within the downcomer region in a PWR model;
within the PWR pressure vessel (PV) at a depth of onefourth 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 182 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 concretespectrumweighted cross sections have been shown to be generally applicable to a wide range of shielding problems. With the neutron and photon flux spectra calculated in the cited spatial locations were produced, in addition, six parameterized cross section sets of selfshielded cross sections for various material mixtures, typical of BWR and PWR compositional models.
RESPONSE FUNCTIONS
The BUGJEFF311.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 (Emid), the group squareroots of Emid 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) and the total (prompt + delayed) neutrons per fission (nu) data for 35 fissionable nuclides. The total neutrons per fission were obtained with two different neutron weighting spectra: flat weighting and 1/4 T PV weighting.
"IAEA IRDF2002 Neutron Dosimeter Cross Sections"
This set of data contains the dosimeter cross sections for all the 71 nuclear reactions included in the IAEA IRDF2002 International Reactor Dosimetry File. The IRDF2002 neutron dosimeter cross sections were processed in the 47 neutron group structure of BUGJEFF311.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 182 materials contained in the infinite dilution cross section set of BUGJEFF311.BOLIB and the photon KERMA factors 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 reactor vessel.
The BUGJEFF311.BOLIB library was generated, through cross section collapsing of the ENEABologna VITJEFF311.BOLIB /5/ finegroup generalpurpose library for nuclear fission applications, using the updated and corrected ENEABologna 2007 Revision /6/ of the ORNL SCAMPI /7/ nuclear data processing system. In particular this ENEABologna version of the SCAMPI system, already transferred to OECDNEA Data Bank (PSR0352/05 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 BUGJEFF311.BOLIB is the same as that used for producing the BUGLE96 library and is consistent with the ANSI/ANS 6.1.21999 (R2009) /8/ American National Standard, reapproved in 2009.
The VITJEFF311.BOLIB cross sections were generated with the LANL NJOY99.259 data processing system and were converted into the AMPX format using the SMILER module of the previously cited ENEABologna 2007 Revision of the SCAMPI system. VITJEFF311.BOLIB is a pseudoproblemindependent library based on the Bondarenko /9/ (ffactor) method for the treatment of neutron resonance selfshielding and temperature effects. It has the same neutron and photon energy group structures (199 neutron groups + 42 photon groups) as the ORNL VITAMINB6 /4/ library in AMPX format (based on ENDF/BVI.3 evaluated nuclear data) from which the BUGLE96 library was generated at ORNL.
The VITJEFF311.BOLIB library contains 182 nuclides: 176 nuclides at 4 temperatures, obtained for the most part with 6 to 8 values for the background cross section. The Fe56 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 VITAMINB6.
Thermal scattering cross sections were processed at all the temperatures available in the JEFF3.1.1 thermal scattering law data file for 6 additional bound nuclides: H1 in light water (HH2O), H1 in polyethylene (HCH2), H1 in zirconium hydride (HZrH), H2 deuterium (D) in heavy water (DD2O), C in graphite (CGph) and Be in beryllium metal thermal (BeTh).
From VITJEFF311.BOLIB it is possible to generate easily, through further proper data processing, working libraries of collapsed and selfshielded cross sections in AMPX format for calculations with the AMPX, SCAMPI and SCALE systems or in FIDOANISN format (as for example the BUGJEFF311.BOLIB library) for calculations with the DOORS and PARTISN deterministic transport systems and finally for calculations with the MORSE Monte Carlo code. This problemdependent data processing must be exclusively performed through the ENEABologna 2007 Revision of the SCAMPI system that can read the binary files generated by NJOY99 with double precision data.
References cited in the present text:
/1/ M. Pescarini, V. Sinitsa, R. Orsi, M. Frisoni, BUGJEFF311.BOLIB  A
JEFF3.1.1 BroadGroup Coupled (47 n + 20 gamma) Cross Section Library
in FIDOANISN Format for LWR Shielding and Pressure Vessel Dosimetry
Applications, ENEABologna Technical Report UTFISSMP9H6002, May 12, 2011.
/2/ The JEFF3.1.1 Nuclear Data Library, JEFF Report 22, OECDNEA Data Bank,
2009.
/3/ The JEFF3.1 Nuclear Data Library, JEFF Report 21, OECDNEA Data Bank,
2006.
/4/ 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 VITAMINB6 FineGroup and the BUGLE96 BroadGroup
Neutron/Photon CrossSection Libraries Derived from ENDF/BVI.3 Nuclear
Data, Oak Ridge, ORNL Report ORNL6795/R1, NUREG/CR6214, Revision 1,
January 1995. The VITAMINB6 library is available from the RSICC and the
OECDNEA Data Bank as DLC0184 ZZ VITAMINB6. The BUGLE96 library is
available from the RSICC and the OECDNEA Data Bank as DLC0185
ZZ BUGLE96.
/5/ M. Pescarini, V. Sinitsa, R. Orsi, VITJEFF311.BOLIB  A JEFF3.1.1
MultiGroup Coupled (199 n + 42 gamma) Cross Section Library in
AMPX Format for Nuclear Fission Applications, ENEABologna
Technical Report UTFISSMP9H6003, in progress.
/6/ V. Sinitsa, M. Pescarini, ENEABologna 2007 Revision of the
SCAMPI (ORNL) Nuclear Data Processing System, ENEABologna
Technical Report FPNP9H6006, September 13, 2007.
The ENEABologna 2007 Revision of the SCAMPI system is available
from the OECDNEA Data Bank as PSR0352/05 SCAMPI.
/7/ SCAMPI: Collection of Codes for Manipulating Multigroup Cross Section
Libraries in AMPX Format, Oak Ridge National Laboratory, RSIC
Peripheral Shielding Routine Collection PSR352, September 1995.
/8/ American National Standard, American Nuclear Society, Neutron and
GammaRay Cross Sections for Nuclear Radiation Protection Calculations
for Nuclear Power Plants, ANSI/ANS6.1.21999 (R2009).
/9/ I.I. Bondarenko, M.N. Nikolaev, L.P. Abagyan, N.O. Bazaziants, Group
Constants for Nuclear Reactors Calculations, Consultants Bureau,
New York, 1964.
/10/ R. Orsi, ADEFTA version 4.1: A Program to Calculate the Atomic
Densities of a Compositional Model for Transport Analysis,
ENEABologna Technical Report FPNP9H6010, May 20, 2008.
The ADEFTA4.1 code is available at the OECDNEA Data Bank
as NEA1708 ADEFTA4.1.
The present package requires about 110 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, selfshielding, shielding.