Computer Programs

NAME OR DESIGNATION, COMPUTER, DESCRIPTION, METHODS, AUXILIARIES, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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To submit a request, click below on the link of the version you wish to order. Rules for end-users are
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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.

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.

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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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.

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.

[ top ]

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).

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).

[ top ]

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

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

[ top ]

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.

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