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NEA-1872 ZZ-BUGENDF70.BOLIB.

ZZ BUGENDF70.BOLIB, ENDF/B-VII.0 Broad-Group Coupled X Sect. Lib. for LWR Shielding & Pressure Vessel Dosimetry Applic.

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1. NAME OR DESIGNATION:  ZZ-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.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
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
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3. DESCRIPTION

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:

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.
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4. METHODS

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.
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-1872/01 11-FEB-2013 Screened
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10. REFERENCES

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.
NEA-1872/01, included references:
References included in the NEA-1872/01 package:

/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.

/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.

/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.
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11. HARDWARE REQUIREMENTS

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).
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

Massimo PESCARINI
ENEA
Italian National Agency for New Technologies, Energy and the Enviroment
"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 Enviroment
"E. Clementel" Research Centre
Bologna - Italy

Manuela FRISONI
ENEA
Italian National Agency for New Technologies, Energy and the Enviroment
"E. Clementel" Research Centre
Bologna - Italy
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16. MATERIAL AVAILABLE
NEA-1872/01
BUGENDF70.BOLIB_INFO.FILE  The information file.
README                     Read-me file including a brief library description.
BUGENDF70.BOLIB            Directory containing the two versions BUGENDF70 and
                           BUGENDF70T of the library, respectively without and
                           with the upscattering cross sections, the response
                           functions and the user's manual.

BUGENDF70                  Directory containing the BUGENDF70 version of the
                           library without thermal upscattering cross sections.
nea1872_01.001.b70         Infinite dilution cross sections, for the 183
                           nuclides contained in BUGENDF70.BOLIB, collapsed with

                           neutron and photon flux spectra for concrete type 04,

                           without thermal upscattering cross sections.
nea1872_01.001.b70_head    Related heading list.
nea1872_01.001.b70_index   Related ANISN identifiers.
nea1872_01.002.b70         Self-shielded cross sections for 24 nuclides,
                           collapsed with neutron and photon flux spectra for
                           PWR core, without thermal upscattering cross
                           sections.
nea1872_01.002.b70_head    Related heading list.
nea1872_01.002.b70_index   Related ANISN identifiers.
nea1872_01.003.b70         Self-shielded cross sections for 17 nuclides,
                           collapsed with neutron and photon flux spectra for
                           PWR downcomer, without thermal upscattering cross
                           sections.
nea1872_01.003.b70_head    Related heading list.
nea1872_01.003.b70_index   Related ANISN identifiers.
nea1872_01.004.b70         Self-shielded cross sections for 15 nuclides,
                           collapsed with neutron and photon flux spectra
                           for PWR pressure vessel (PV) at 1/4 thickness (T),
                           without thermal upscattering cross sections.
nea1872_01.004.b70_head    Related heading list.
nea1872_01.004.b70_index   Related ANISN identifiers.
nea1872_01.005.b70         Self-shielded cross sections for 24 nuclides,
                           collapsed with neutron and photon flux spectra for
                           concrete type 04, without thermal upscattering cross
                           sections.
nea1872_01.005.b70_head    Related heading list.
nea1872_01.005.b70_index   Related ANISN identifiers.
nea1872_01.006.b70         Self-shielded cross sections for 15 nuclides in
                           carbon steel and 15 nuclides in stainless steel,
                           collapsed with neutron and photon flux spectra
                           for PWR pressure vessel (PV) at 1/4 thickness (T),
                           without thermal upscattering cross sections.
nea1872_01.006.b70_head    Related heading list.
nea1872_01.006.b70_index   Related ANISN identifiers.
nea1872_01.007.b70         Self-shielded cross sections for 14 nuclides,
                           collapsed  with neutron and photon flux spectra
                           for BWR core, without thermal upscattering cross
                           sections.
nea1872_01.007.b70_head    Related heading list.
nea1872_01.007.b70_index   Related ANISN identifiers.

BUGENDF70T                 Directory containing the BUGENDF70T version of the
                           library with thermal upscattering cross sections
                           retained.
nea1872_01.008.b70         Infinite dilution cross sections, for the 183
                           nuclides contained in BUGENDF70T.BOLIB, collapsed
                           with neutron and photon flux spectra for concrete
                           type 04, with thermal upscattering cross sections
                           retained.
nea1872_01.008.b70_head    Related heading list.
nea1872_01.008.b70_index   Related ANISN identifiers.
nea1872_01.009.b70         Self-shielded cross sections for 24 nuclides,
                           collapsed with neutron and photon flux spectra for
                           PWR core, with thermal upscattering cross sections
                           retained.
nea1872_01.009.b70_head    Related heading list.
nea1872_01.009.b70_index   Related ANISN identifiers.
nea1872_01.010.b70         Self-shielded cross sections for 17 nuclides,
                           collapsed with neutron and photon flux spectra for
                           PWR downcomer, with thermal upscattering cross
                           sections retained.
nea1872_01.010.b70_head    Related heading list.
nea1872_01.010.b70_index   Related ANISN identifiers.
nea1872_01.011.b70         Self-shielded cross sections for 15 nuclides,
                           collapsed with neutron and photon flux spectra
                           for PWR pressure vessel (PV) at 1/4 thickness (T),
                           with thermal upscattering cross sections retained.
nea1872_01.011.b70_head    Related heading list.
nea1872_01.011.b70_index   Related ANISN identifiers.
nea1872_01.012.b70         Self-shielded cross sections for 24 nuclides,
                           collapsed with neutron and photon flux spectra for
                           concrete type 04, with thermal upscattering cross
                           sections retained.
nea1872_01.012.b70_head    Related heading list.
nea1872_01.012.b70_index   Related ANISN identifiers.
nea1872_01.013.b70         Self-shielded cross sections for 15 nuclides in
                           carbon steel and 15 nuclides in stainless steel,
                           collapsed with neutron and photon flux spectra
                           for PWR pressure vessel (PV) at 1/4 thickness (T),
                           with thermal upscattering cross sections retained.
nea1872_01.013.b70_head    Related heading list.
nea1872_01.013.b70_index   Related ANISN identifiers.
nea1872_01.014.b70         Self-shielded cross sections for 14 nuclides,
                           collapsed with neutron and photon flux spectra for
                           BWR core, with thermal upscattering cross sections
                           retained.
nea1872_01.014.b70_head    Related heading list.
nea1872_01.014.b70_index   Related ANISN identifiers.

ADEFTA_for_GIP             Directory containing the BUGENDF70 and BUGENDF70T
                           cross section files addressed to be handled by the
                           ENEA-Bologna ADEFTA-4.1 code in order to produce a
                           GIP input to run the ANISN, DORT and TORT transport
                           codes.
bugb70_01_to_07_gip        File corresponding to the 14** array of a GIP code
                           input, obtained by appending in sequence files of
                           BUGENDF70.
bugb70_01_to_07_gip.index  File with ANISN identifiers related to the previous
                           file to be input to the ADEFTA code.
bugb70t_08_to_14_gip       File corresponding to the 14** array of a GIP code
                           input, obtained by appending in sequence files of
                           BUGENDF70T.
bugb70t_08_to_14_gip.index File with ANISN identifiers related to the previous
                           file to be input to the ADEFTA code.

Response_Functions         Directory containing the "General Neutron Response
                           Functions", the "Total (prompt + delayed) Neutron
                           Fission Spectra (chi)" for 34 fissionable nuclides,
                           the "Total (prompt + delayed) Neutrons per Fission
                           (nu)" for 35 fissionable nuclides, the "IAEA
                           IRDF-2002 Neutron Dosimeter Cross Sections" for 71
                           nuclear reactions and the "Neutron and Photon
                           KERMA Factors".
general_n_responses        "General Neutron Response Functions", including the
                           BUGENDF70.BOLIB 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 to get 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_n_fiss_spectra       Directory containing the "Total (prompt + delayed)
                           Neutron Fission Spectra (chi)" for 34 fissionable
                           nuclides.
total_n_chi.b70            Total neutron fission spectra (chi).
fiss_xs_flat.b70           Fission cross sections (flat weighting) for 35
                           fissionable nuclides.
fiss_nuclide_list          List of the fissionable nuclides for which the
                           total neutron fission spectra are available.

total_nu                   Directory containing the "Total (prompt + delayed)
                           Neutrons per Fission (nu)" for 35 fissionable
                           nuclides.
nu_Flat.b70                Total neutrons per fission (nu) (flat weighting).
nu_14tpv.b70               Total neutrons per fission (nu) (1/4 T PV weighting).

n_dosimeter_xs             Directory containing the "IAEA IRDF-2002 Neutron
                           Dosimeter Cross Sections", including dosimeter cross
                           sections obtained with two flux weightings
                           (flat weighting and 1/4 T PV weighting) in the 47
                           neutron group structure of BUGENDF70.BOLIB, for all
                           the 71 nuclear reactions contained in the IAEA
                           International Reactor Dosimetry File IRDF-2002.
n_dosimeter_flat           IAEA IRDF-2002 neutron dosimeter cross sections
                           (flat weighting).
n_dosimeter_14tpv          IAEA IRDF-2002 neutron dosimeter cross sections
                           (1/4 T PV weighting).

kerma_factors              Directory containing the "Neutron and Photon KERMA
                           Factors".
neutron_kerma.b70          Neutron KERMA factors (eV x barns) for 183 nuclides.
neutron_kerma_list         List of the 183 nuclides contained in BUGENDF70.BOLIB

                           for which the neutron KERMA factors are available.
photon_kerma.b70           Photon KERMA factors (eV x barns) for 53 natural
                           elements.
photon_kerma_list          List of the 53 natural elements corresponding to the
                           183 nuclides contained in BUGENDF70.BOLIB for which
                           the photon KERMA factors are available.

DOC                        Documentation directory.
UTFISSM-P9H6-008_rev0.pdf  User's manual of the ENEA-Bologna BUGENDF70.BOLIB
                           library.
FPN-P9H6-006_rev0.pdf      Report of the ENEA-Bologna 2007 Revision (Available
                           at OECD-NEA Data Bank as PSR-0352/05 SCAMPI) of the
                           ORNL SCAMPI nuclear data processing system.
FPN-P9H6-010_rev0.pdf      User's manual of the ENEA-Bologna ADEFTA-4.1 code.
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: LWR reactors, data library, multigroup, pressure vessels, pwr reactors, self-shielding, shielding.