1,720,974 research outputs found
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment
No full textThree-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the Iron-88 single-material (Fe) neutron shielding benchmark experiment were performed using the TORT-3.2 discrete ordinates (SN) transport code. The ENEA-Bologna BUGJEFF311.BOLIB (JEFF-3.1.1 data) and BUGENDF70.BOLIB (ENDF/B-VII.0 data) broad-group coupled (47 n + 20 ) working cross section libraries in FIDO-ANISN format together with the similar ORNL BUGLE-B7 (ENDF/B-VII.0 data) and BUGLE-96 (ENDF/B-VI.3 data) libraries, specifically conceived for LWR shielding and pressure vessel dosimetry applications, were alternatively used together with dosimeter cross sections, processed from the IAEA IRDF-2002 dosimetry file. The ENEA-Bologna programs ADEFTA-4.1 and BOT3P-5.3 were respectively employed for the calculation of the isotopic atomic densities and for the automatic generation of the spatial mesh grid of the geometrical model. The calculated dosimetric results were compared with the corresponding experimental data, obtained with Au-198(n,γ)Au-198 activation dosimeters and with Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24 threshold activation dosimeters. Given the total experimental uncertainties at 1σ, then the computational results presented exhibit good statistical consistency with the corresponding measurements except for the Al-27(n,α)Na-24 strongly overestimated results
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra
No full textThe whole set of the dosimetry point-wise cross sections of the International Reactor Dosimetry File IRDF-2002 were processed in the 47 neutron group structure of the ORNL BUGLE-96 broad-group cross section working library for LWR shielding applications through the GROUPIE program of the PREPRO 2007 nuclear data processing system.
The reported 47 energy group response functions were calculated for all the following weighting spectrum conditions:
• flat weighting spectrum;
• 1/4 T (T = LWR pressure vessel thickness) pressure vessel weighting spectrum obtained from transport calculations using cross sections based on the JEFF-3.1.1 evaluated nuclear data library and processed with the NJOY-99.259 nuclear data processing system;
• 1/4 T pressure vessel weighting spectrum obtained from transport calculations using cross sections based on the ENDF/B- VII.0 evaluated nuclear data library and processed with the NJOY -99.259 nuclear data processing system
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment
No full textFinal results concerning the ENEA-Bologna BUGJEFF311.BOLIB working cross section library validation on the Iron-88 single material (iron) integral neutron shielding benchmark experiment are presented. The BUGJEFF311.BOLIB library is specifically dedicated to LWR shielding and pressure vessel dosimetry applications. It is a broad-group coupled (47 n + 20 ) working library in FIDO-ANISN format, based on the OECD-NEADB JEFF-3.1.1 evaluated nuclear data library and with the same group structure as the ORNL BUGLE-96 similar library. The analysis of the Iron-88 Winfrith benchmark experiment was performed through 3D transport calculations in Cartesian geometry using the ORNL TORT-3.2 discrete ordinates (SN) code together with the BUGJEFF311.BOLIB library and the BUGLE-96 library as term of comparison. The activation cross sections for the Au-198(n,γ)Au-198 dosimeters and the threshold activation cross sections for the Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24 dosimeters were derived from the IAEA IRDF-2002 reactor dosimetry file
Iron-88 (Fe) Neutron Shielding Benchmark Experiment - Deterministic Analysis in Cartesian (X,Y,Z) Geometry Using the TORT-3.2 3D Transport Code and the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries
No full textThree-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the Iron-88 single-material (Fe) neutron shielding benchmark experiment were performed using the TORT-3.2 discrete ordinates (SN) transport code. The ENEA-Bologna BUGJEFF311.BOLIB (JEFF-3.1.1 data) and BUGENDF70.BOLIB (ENDF/B-VII.0 data) broad-group coupled (47 n + 20 γ) working cross section libraries in FIDO-ANISN format and the similar ORNL BUGLE-B7 (ENDF/B-VII.0 data) and BUGLE-96 (ENDF/B-VI.3 data) libraries, specifically conceived for LWR shielding and pressure vessel dosimetry applications, were alternatively used together with dosimeter cross sections, processed from the IAEA IRDF-2002 dosimetry file. The ENEA-Bologna codes ADEFTA-4.1 and BOT3P-5.3 were respectively employed for the calculation of the isotopic atomic densities and for the automatic generation of the spatial mesh grid of the geometrical model. The calculated reaction rates were compared with the corresponding experimental data, obtained using Au-197(n,γ)Au-198/Cd activation dosimeters and Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24 threshold activation dosimeters. Given the total experimental uncertainties at 1σ, then the computational results presented exhibit good statistical consistency with the corresponding measurements except for the Al-27(n,α)Na-24 strongly overestimated results
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment
No full textPreliminary results concerning the ENEA-Bologna BUGJEFF311.BOLIB working cross section library validation on the Iron-88 single material (iron) integral neutron shielding benchmark experiment are presented. The BUGJEFF311.BOLIB library is specifically dedicated to LWR shielding and pressure vessel dosimetry applications. It is a broad-group coupled (47 n + 20 ) working library in FIDO-ANISN format, based on the OECD-NEADB JEFF-3.1.1 evaluated nuclear data library and with the same group structure as the ORNL BUGLE-96 similar library. The analysis of the Iron-88 Winfrith benchmark experiment was performed through 3D transport calculations in Cartesian geometry using the ORNL TORT-3.2 discrete ordinates (SN) code, the BUGJEFF311.BOLIB library and the threshold activation dosimeter cross sections for Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24, derived from the IAEA IRDF-2002 reactor dosimetry file
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment
No full textThree-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the PCA-Replica 12/13 water/iron (H2O/Fe) engineering neutron shielding benchmark experiment were performed with the TORT-3.2 discrete ordinates (SN) code. The ENEA-Bologna BUGJEFF311.BOLIB (JEFF-3.1.1 data) and BUGENDF70.BOLIB (ENDF/B-VII.0 data) broad-group coupled (47 n + 20 γ) working cross section libraries in FIDO-ANISN format together with the similar ORNL BUGLE-96 (ENDF/B-VI.3 data) library, specifically conceived for LWR shielding and pressure vessel dosimetry applications, were alternatively used together with dosimeter cross sections, processed from the IAEA IRDF-2002 dosimetry file. The ENEA-Bologna programs ADEFTA-4.1 and BOT3P-5.3 were respectively employed for the calculation of the isotopic atomic densities and for the automatic generation of the spatial mesh grid of the geometrical model. The calculated integral and spectral results were compared with the corresponding experimental data, respectively obtained with threshold activation dosimeters (Rh-103(n,n')Rh-103m, In-115(n,n')In-115m and S-32(n,p)P-32), spherical hydrogen-filled proportional counters (type SP-2) and a spherical organic liquid (NE213) scintillator. PCA-Replica, reproducing the ex-core geometry of a PWR, is particularly fit to test the cited working libraries since it was specifically conceived to check calculated fast neutron fluxes in a PWR mild steel pressure vessel simulator
PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment - Deterministic Analysis in Cartesian (X,Y,Z) Geometry Using the TORT-3.2 3D Transport Code and the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries
No full textThree-dimensional (3D) fixed source transport calculations in Cartesian (X,Y,Z) geometry for the PCA-Replica 12/13 water/iron (H2O/Fe) engineering neutron shielding benchmark experiment were performed using the TORT-3.2 discrete ordinates (SN) code. The ENEA-Bologna BUGJEFF311.BOLIB (JEFF-3.1.1 data) and BUGENDF70.BOLIB (ENDF/B-VII.0 data) broad-group coupled (47 n + 20 ) working cross section libraries in FIDO-ANISN format together with the similar ORNL BUGLE-96 (ENDF/B-VI.3 data) library, specifically conceived for LWR shielding and pressure vessel dosimetry applications, were alternatively used together with dosimeter cross sections, processed from the IAEA IRDF-2002 dosimetry file. The ENEA-Bologna programs ADEFTA-4.1 and BOT3P-5.3 were respectively employed for the calculation of the isotopic atomic densities and for the automatic generation of the spatial mesh grid of the geometrical model. The calculated dosimetric and spectral results were compared with the corresponding experimental data, respectively obtained with threshold activation dosimeters (Rh-103(n,n')Rh-103m, In-115(n,n')In-115m and S-32(n,p)P-32), spherical hydrogen-filled proportional counters (type SP-2) and a spherical organic liquid (NE213) scintillator. Given the total experimental uncertainties at 1σ, then the computational results presented exhibit very good statistical consistency with the corresponding measurements. PCA-Replica, reproducing the ex-core radial geometry of a PWR, is particularly fit to test the cited working libraries since it was specifically conceived to check calculated fast neutron fluxes in a PWR mild steel pressure vessel simulator
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data
No full textThe ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled (199 n + 42 γ) cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated nuclear data library. The generation of the VITJEFF32.BOLIB library for nuclear fission applications was conceived as an European counterpart of the ORNL VITAMIN-B7 library based on ENDF/B-VII.0 data. The present library has the same neutron/photon energy group structure and general features as the former ORNL VITAMIN-B6 reference library and was produced using similar data processing methodologies, based on the NJOY-2012.53 and SCAMPI nuclear data processing systems. VITJEFF32.BOLIB is a pseudo-problem-independent library based on the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 184 standard (not bound) nuclides singularly processed at 4 temperatures (300, 600, 1000 and 2100 K) and at 11 background cross sections. Thermal scattering cross sections were processed at all the temperatures available in the JEFF-3.2 thermal scattering law data file for 6 additional bound nuclides: H-1 in light water, H-1 in polyethylene, H-1 in zirconium hydride, H-2 in heavy water, C in graphite and Be in beryllium metal. From VITJEFF32.BOLIB it is possible to generate, through the ENEA-Bologna 2007 Revision of SCAMPI, collapsed working libraries of self-shielded cross sections in AMPX or FIDO-ANISN format for LWR applications
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications
No full textThe ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled (199 n + 42 γ) cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated nuclear data library. The generation of the VITJEFF32.BOLIB library for nuclear fission applications was conceived as an European counterpart of the ORNL VITAMIN-B7 library based on ENDF/B-VII.0 data. The present library has the same neutron/photon energy group structure and general features as the former ORNL VITAMIN-B6 reference library and was produced using similar data processing methodologies, based on the NJOY-2012.53 and SCAMPI nuclear data processing systems. VITJEFF32.BOLIB is a pseudo-problem-independent library based on the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. The library contains 184 standard (not bound) nuclides singularly processed at 4 temperatures (300, 600, 1000 and 2100 K) and at 12 background cross sections. Thermal scattering cross sections were processed at all the temperatures available in the JEFF-3.2 thermal scattering law data file for 6 additional bound nuclides: H-1 in light water, H-1 in polyethylene, H-1 in zirconium hydride, H-2 in heavy water, C in graphite and Be in beryllium metal. From VITJEFF32.BOLIB it is possible to generate, through the ENEA-Bologna 2007 Revision of SCAMPI, collapsed working libraries of self-shielded cross sections in AMPX or FIDO-ANISN format for LWR applications
Three-Dimensional (X,Y,Z) Deterministic Analysis of the PCA-Replica Neutron Shielding Benchmark Experiment Using the TORT-3.2 Code and Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry
Full text linkThe PCA-Replica 12/13 (H2O/Fe) neutron shielding benchmark experiment was analysed using the ORNL TORT-3.2 3D SN code. PCA-Replica, specifically conceived to test the accuracy of nuclear data and transport codes employed in LWR shielding and radiation damage calculations, reproduces a PWR ex-core radial geometry with alternate layers of water and steel including a PWR pressure vessel simulator. Three broad-group coupled neutron/photon working cross section libraries in FIDO-ANISN format with the same energy group structure (47 n + 20 γ) and based on different nuclear data were alternatively used: the ENEA BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) libraries and the ORNL BUGLE-96 (ENDF/B-VI.3) library. Dosimeter cross sections derived from the IAEA IRDF-2002 dosimetry file were employed. The calculated reaction rates for the Rh-103(n,n')Rh-103m, In-115(n,n')In-115m and S-32(n,p)P-32 threshold activation dosimeters and the calculated neutron spectra are compared with the corresponding experimental results
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