PESCARINI, MASSIMO
 Distribuzione geografica
Continente #
NA - Nord America 1.608
EU - Europa 946
AS - Asia 216
Continente sconosciuto - Info sul continente non disponibili 16
SA - Sud America 7
OC - Oceania 2
AF - Africa 1
Totale 2.796
Nazione #
US - Stati Uniti d'America 1.441
GB - Regno Unito 290
SE - Svezia 280
CA - Canada 167
IT - Italia 126
CN - Cina 98
DE - Germania 84
RU - Federazione Russa 56
HK - Hong Kong 36
VN - Vietnam 36
BE - Belgio 27
FI - Finlandia 27
FR - Francia 27
EU - Europa 16
SG - Singapore 13
IN - India 11
UA - Ucraina 11
JP - Giappone 10
BR - Brasile 7
KR - Corea 7
ES - Italia 6
NL - Olanda 5
CH - Svizzera 3
IQ - Iraq 2
IR - Iran 2
RO - Romania 2
AU - Australia 1
IE - Irlanda 1
NZ - Nuova Zelanda 1
PK - Pakistan 1
SI - Slovenia 1
ZA - Sudafrica 1
Totale 2.796
Città #
Chandler 598
San Mateo 170
Southend 167
Toronto 167
New York 88
Boardman 61
Berlin 57
Ashburn 47
Dong Ket 36
Hong Kong 36
Trenton 34
Beijing 32
Washington 28
Brussels 27
Helsinki 26
Las Vegas 22
Ann Arbor 19
Mountain View 18
Marseille 15
Rome 12
Redwood City 10
Zhengzhou 10
Kyiv 7
Los Angeles 7
Hanover 6
Mazzano Romano 6
Miami 6
Paris 6
Singapore 6
Bologna 5
Bruino 5
Tampa 5
Dallas 4
Herzberg 4
Borås 3
Changsha 3
Magdeburg 3
Moscow 3
Redmond 3
Rockville 3
Shanghai 3
Barceloneta 2
Clifton 2
Des Moines 2
Gatchina 2
Horia 2
Madrid 2
Milan 2
Mosul 2
Saint-Fons 2
Torrelavega 2
Auckland 1
Bangalore 1
Bourg-la-Reine 1
Brooklyn 1
Cambridge 1
Chicago 1
Danbury 1
Dublin 1
Forest City 1
Frosinone 1
Gwanak-gu 1
Hangyang 1
Ibra 1
Iglesias 1
Lausanne 1
Ljubljana 1
Monterotondo 1
Montopoli in Val d'Arno 1
Nanjing 1
Naples 1
North Hollywood 1
Omsk 1
Parma 1
Ravenna 1
Reggio Calabria 1
San Pietro in Casale 1
Sarno 1
Serra Riccò 1
St Petersburg 1
Sydney 1
Torre Boldone 1
Venezia 1
West Orange 1
Whitehaven 1
Xian 1
Zurich 1
Totale 1.824
Nome #
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 121
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report 80
BUGENDF70.BOLIB – An ENDF/B-VII.0 Broad-Group Coupled (47n+20 γ) Cross Section Library in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications 77
BUGENDF70.BOLIB - An ENEA-Bologna ENDF/B-VII.0 Cross Section Library (47 n + 20 γ) in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications 70
BUGJEFF311.BOLIB - A JEFF-3.1.1 Broad-Group Coupled (47 n + 20 γ) Cross Section Library in FIDO-ANISN Format for LWR Shielding and Pressure Vessel Dosimetry Applications 66
JENDL-3.1 and ENDF/B VI Iron Validation on the (H2O/FE) PCA-REPLICA Shielding Benchmark 61
Data Processing and Validation Needs of Group-Wise Working Cross Section Libraries for Nuclear Fission Reactor Shielding and Radiation Damage Applications 61
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 61
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 59
ENEA-Bologna Multi-Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry Applications 57
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 56
BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) - Generation Methodology and Preliminary Testing of two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry 56
BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) - Generation Methodology and Preliminary Testing of Two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry 55
ENEA-Bologna 2007 Revision of the SCAMPI (ORNL) Nuclear Data Processing System 54
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format 54
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment 53
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 53
A Neutron Cross Section Evaluation for Th-232 in the En &l 20 MeV Energy Range 51
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data 50
A Neutron Cross Section Evaluation for 232Th in the En <20 MeV Energy Range 49
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 49
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code 49
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 48
ENEA-BOLOGNA PRODUCTION AND TESTING OF JEF-2.2 MULTI-GROUP CROSS SECTION LIBRARIES FOR NUCLEAR FISSION APPLICATIONS 47
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment 47
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 47
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications 46
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 46
AUTOMATIC GENERATION OF 3D FINE MESH GEOMETRIES FOR THE ANALYSIS OF TRE VENUS-3 SHIELDING BENCHMARK EXPERIMENT WITH THE TORT CODE. Paper presented at:International Conference on 46
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 46
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705 46
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 45
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method 45
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code 44
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code 44
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 44
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results 43
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment 43
JENDL-3.1 Iron Validation on the PCA-Replica (H2O/FE), Shielding Benchmark Experiment - JEFF/DOC-703 42
VITJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 42
Generation and Preliminary Testing of ENEA-Bologna BUGLE-Type Group Libraries Based on JEFF-3.1 and ENDF/B-VII.0 Nuclear Data for LWR Shielding and Pressure Vessel Dosimetry 42
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations 42
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 42
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations 41
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment 40
Production and testing of the ENEA-Bologna VITJEFF32.BOLIB (JEFF-3.2) multi-group (199 n + 42 γ) cross section library in AMPX format for nuclear fission applications 40
ENEA-BOLOGNA NUCLEAR DATA CENTRE - A Summary of the Main Objectives Achieved in the Period 1997-2001 39
Status of the JEFF Nuclear Data Library 39
VITENDF70.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on ENDF/B - VII.0 Data 38
VITJEF22.BOLIB - A JEF-2.2 MULTIGROUP COUPLED (199 n + 42 gamma) CROSS SECTION LIBRARY IN AMPX FORMAT FOR NUCLEAR FISSION APPLICATIONS 37
A Review of the Activities of the Nuclear Data Center at ENEA 37
MATJEF22.BOLIB - A JEF-2.2 MULTIGROUP COUPLED (199 n + 42 gamma) CROSS SECTION LIBRARY IN MATXS FORMAT FOR NUCLEAR FISSION APPLICATIONS 36
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra 36
MATJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42gamma) Cross Section Library in MATXS Format for Nuclear Fission Applications 36
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 35
PCA-Replica Shielding Benchmark: Final Comparison of the Validations of the JENDL-3.1 and ENDF/B VI Iron Cross Sections Sets, JEF/DOC-581, JEF 32
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment 31
Totale 2.796
Categoria #
all - tutte 20.137
article - articoli 0
book - libri 0
conference - conferenze 0
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 20.137


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202026 0 0 0 0 4 2 3 2 3 8 4 0
2020/2021433 1 6 0 13 128 0 3 44 19 15 168 36
2021/2022640 9 171 18 23 90 17 31 162 25 5 42 47
2022/20231.107 66 227 77 146 50 197 7 104 167 23 26 17
2023/2024583 42 22 73 5 58 121 14 38 78 36 19 77
2024/20257 7 0 0 0 0 0 0 0 0 0 0 0
Totale 2.796