last modified: 03-APR-2013 | catalog | categories | new | search |

NEA-1866 ZZ-BUGJEFF311.BOLIB.

ZZ BUGJEFF311.BOLIB, JEFF-3.1.1 Broad-Group Coupled X Sect Lib. for LWR Shielding & Pressure Vessel Dosimetry Applic.

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1. NAME OR DESIGNATION:  ZZ-BUGJEFF311.BOLIB
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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-BUGJEFF311.BOLIB NEA-1866/02 Tested 03-APR-2013

Machines used:

Package ID Orig. computer Test computer
NEA-1866/02 Many Computers Linux-based PC
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3. DESCRIPTION

The ENEA-Bologna Nuclear Data Group generated the BUGJEFF311.BOLIB /1/ library in FIDO-ANISN format. BUGJEFF311.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 OECD-NEA Data Bank JEFF-3.1.1 /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 BUGLE-96 /4/ similar library generated at ORNL in 1996, based on ENDF/B-VI.3 evaluated nuclear data. BUGJEFF311.BOLIB was produced from the ENEA-Bologna VITJEFF311.BOLIB /5/ fine-group mother library in AMPX format, based on JEFF-3.1.1 data.
The fine-group data of VITJEFF311.BOLIB were collapsed and in some cases self-shielded, through the ENEA-Bologna 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 ENEA-BOLOGNA VITJEFF311.BOLIB and BUGJEFF311.BOLIB libraries can be respectively considered as European counterparts of the ORNL VITAMIN-B6 /4/ and BUGLE-96 libraries. BUGJEFF311.BOLIB, differently from BUGLE-96 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
                    self-shielded 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 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.
                    
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 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: JEFF-3.1.1

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: 182

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-nat   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 BUGJEFF311.BOLIB cross sections through VITJEFF311.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 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 concrete-spectrum-weighted 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 self-shielded 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 (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) 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 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 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.
NEA-1866/02
NEW VERSION DIFFERS FROM PREVIOUS VERSION
-----------------------------------------
The manual UTFISSM-P9H6-002 has been updated to make several minor corrections and improve the text.
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4. METHODS

The BUGJEFF311.BOLIB library was generated, through cross section collapsing of the ENEA-Bologna VITJEFF311.BOLIB /5/ fine-group general-purpose library for nuclear fission applications, using the updated and corrected ENEA-Bologna 2007 Revision /6/ of the ORNL SCAMPI /7/ 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 BUGJEFF311.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) /8/ American National Standard, reapproved in 2009.

The VITJEFF311.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. VITJEFF311.BOLIB is a pseudo-problem-independent library based on the Bondarenko /9/ (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 /4/ library in AMPX format (based on ENDF/B-VI.3 evaluated nuclear data) from which the BUGLE-96 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 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 JEFF-3.1.1 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 VITJEFF311.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 BUGJEFF311.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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9. STATUS
Package ID Status date Status
NEA-1866/02 03-APR-2013 Tested at NEADB
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10. REFERENCES

References cited in the present text:

/1/  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.

/2/  The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD-NEA Data Bank,
     2009.

/3/  The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD-NEA 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 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. The VITAMIN-B6 library is available from the RSICC and the
     OECD-NEA Data Bank as DLC-0184 ZZ VITAMIN-B6. The BUGLE-96 library is
     available from the RSICC and the OECD-NEA Data Bank as DLC-0185
     ZZ BUGLE-96.

/5/  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, in progress.

/6/  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.

/7/  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.

/8/  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).

/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,
     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-1866/02, included references:
References cited in the present text and included in the NEA-1866/02 package:

/1/  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_rev1, March 14,
2013.

/6/  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.

/10/ 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 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).
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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 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
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16. MATERIAL AVAILABLE
NEA-1866/02
BUGJEFF311.BOLIB_INFO.FILE           The information file.
README                               Read-me file including a brief library
                                     description.
BUGJEFF311.BOLIB                     Directory containing the two versions
                                     BUGJEFF311 and BUGJEFF311T of the library,
                                     respectively without and with the
                                     upscattering cross sections, the response
                                     functions and the user's manual.
BUGJEFF311                           Directory containing the BUGJEFF311
                                     version of the library without thermal
                                     upscattering cross sections.
nea1866_01.001.jeff311               Infinite dilution cross sections for the
                                     182 nuclides contained
                                     in BUGJEFF311.BOLIB, collapsed with
                                     neutron and photon flux spectra for
                                     concrete type 04, without thermal
                                     upscattering cross sections.
nea1866_01.001.jeff311_head          Related heading list.
nea1866_01.001.jeff311_index         Related ANISN identifiers.
nea1866_01.002.jeff311               Self-shielded cross sections for 24
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for PWR core,
                                     without thermal upscattering cross
                                     sections.
nea1866_01.002.jeff311_head          Related heading list.
nea1866_01.002.jeff311_index         Related ANISN identifiers.
nea1866_01.003.jeff311               Self-shielded cross sections for 17
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for PWR downcomer,
                                     without thermal upscattering cross
                                     sections.
nea1866_01.003.jeff311_head          Related heading list.
nea1866_01.003.jeff311_index         Related ANISN identifiers.
nea1866_01.004.jeff311               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.
nea1866_01.004.jeff311_head          Related heading list.
nea1866_01.004.jeff311_index         Related ANISN identifiers.
nea1866_01.005.jeff311               Self-shielded cross sections for 24
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for concrete type 04,
                                     without thermal upscattering cross
                                     sections.
nea1866_01.005.jeff311_head          Related heading list.
nea1866_01.005.jeff311_index         Related ANISN identifiers.
nea1866_01.006.jeff311               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.
nea1866_01.006.jeff311_head          Related heading list.
nea1866_01.006.jeff311_index         Related ANISN identifiers.
nea1866_01.007.jeff311               Self-shielded cross sections for 14
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for BWR core, without
                                     thermal upscattering cross sections.
nea1866_01.007.jeff311_head          Related heading list.
nea1866_01.007.jeff311_index         Related ANISN identifiers.
BUGJEFF311T                          Directory containing the BUGJEFF311T
                                     version of the library with thermal
                                     upscattering cross sections retained.
nea1866_01.008.jeff311               Infinite dilution cross sections for the
                                     182 nuclides contained in
                                     BUGJEFF311T.BOLIB, collapsed with neutron
                                     and photon flux spectra for concrete
                                     type 04, with thermal upscattering cross
                                     sections retained.
nea1866_01.008.jeff311_head          Related heading list.
nea1866_01.008.jeff311_index         Related ANISN identifiers.
nea1866_01.009.jeff311               Self-shielded cross sections for 24
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for PWR core,
                                     with thermal upscattering cross sections
                                     retained.
nea1866_01.009.jeff311_head          Related heading list.
nea1866_01.009.jeff311_index         Related ANISN identifiers.
nea1866_01.010.jeff311               Self-shielded cross sections for 17
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for PWR downcomer,
                                     with thermal upscattering cross sections
                                     retained.
nea1866_01.010.jeff311_head          Related heading list.
nea1866_01.010.jeff311_index         Related ANISN identifiers.
nea1866_01.011.jeff311               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.
nea1866_01.011.jeff311_head          Related heading list.
nea1866_01.011.jeff311_index         Related ANISN identifiers.
nea1866_01.012.jeff311               Self-shielded cross sections for 24
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for concrete type 04,
                                     with thermal upscattering cross sections
                                     retained.
nea1866_01.012.jeff311_head          Related heading list.
nea1866_01.012.jeff311_index         Related ANISN identifiers.
nea1866_01.013.jeff311               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.
nea1866_01.013.jeff311_head          Related heading list.
nea1866_01.013.jeff311_index         Related ANISN identifiers.
nea1866_01.014.jeff311               Self-shielded cross sections for 14
                                     nuclides, collapsed with neutron and
                                     photon flux spectra for BWR core,
                                     with thermal upscattering cross sections
                                     retained.
nea1866_01.014.jeff311_head          Related heading list.
nea1866_01.014.jeff311_index         Related ANISN identifiers.
ADEFTA_for_GIP                       Directory containing the BUGJEFF311 and
                                     BUGJEFF311T cross section files addressed
                                     to be handled by the ENEA-BOLOGNA
                                     ADEFTA-4.1 /10/ code in order to produce
                                     a GIP input to run the ANISN, DORT and
                                     TORT transport codes.
bugjeff311_01_to_07_gip              File corresponding to the 14** array of a
                                     GIP code input, obtained by appending in
                                     sequence files of BUGJEFF311.
bugjeff311_01_to_07_gip.index        File with ANISN identifiers related to
                                     the file bugjeff311_01_to_07_gip to be
                                     input to the ADEFTA code.
bugjeff311t_08_to_14_gip             File corresponding to the 14** array of
                                     a GIP code input, obtained by appending
                                     in sequence files of BUGJEFF311T.
bugjeff311t_08_to_14_gip.index       File with ANISN identifiers related to the
                                     file bugjeff311t_08_to_14_gip 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 35 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 BUGJEFF311. 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 35 fissionable nuclides.
total_n_chi.jeff311                  Total neutron fission spectra (chi).
fiss_xs_flat.jeff311                 Fission cross sections (flat weighting)
                                     for 35 fissionable nuclides.
fiss_nuclide_list                    List of the 35 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.jeff311                      Total neutrons per fission (nu)
                                     (flat weighting).
nu_14tpv.jeff311                     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
                                     for all the 71 nuclear reactions
                                     contained in the IAEA International
                                     Reactor Dosimetry File IRDF-2002,
                                     obtained with two flux weightings
                                     (flat weighting and 1/4 T PV weighting)
                                     in the 47 neutron group structure of
                                     BUGJEFF311.BOLIB.
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.jeff311                Neutron KERMA factors (eV x barns) for
                                     182 nuclides.
neutron_kerma_list                   List of the 182 nuclides contained in
                                     BUGJEFF311.BOLIB for which the neutron
                                     KERMA factors are available.
photon_kerma.jeff311                 Photon KERMA factors (eV x barns) for
                                     53 natural elements.
photon_kerma_list                    List of the 53 natural elements
                                     corresponding to the 182 nuclides
                                     contained in BUGJEFF311.BOLIB for which
                                     the photon KERMA factors are available.
DOC                                  Documentation directory.
UTFISSM-P9H6-002_rev1.pdf            User's manual of the ENEA-Bologna
                                     NEA-1866/02 ZZ BUGJEFF311.BOLIB
                                     library.
FPN-P9H6-006_rev0.pdf                Report of the ENEA-Bologna 2007 Revision
                                     (PSR-0352/05 SCAMPI)of the ORNL SCAMPI
                                     nuclear data processing system.
FPN-P9H6-010_rev0.pdf                User's manual of the ENEA-Bologna
                                     NEA-1708 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.