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.
NAME OR DESIGNATION, COMPUTER, DESCRIPTION, METHODS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| 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.
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.
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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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.
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.
[ top ]
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).
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).
[ top ]
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
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
[ top ]
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.
Keywords: LWR reactors, data library, multigroup, pressure vessels, pwr reactors, self-shielding, shielding.