ENEA-IRIS Open Archive è l’archivio della produzione scientifica dell'ENEA, realizzato con l'obiettivo di raccogliere, catalogare e rendere facilmente accessibili in rete i risultati della ricerca. Gli autori dell’ENEA provvedono a depositare le proprie pubblicazioni (articoli su rivista, presentazioni a congressi, report, ecc.). In particolare, quelle finanziate dalla Commissione Europea nell’ambito del programma H2020 (che prevede il deposito obbligatorio in un Repository), una volta caricate, vengono automaticamente importate dal portale europeo OpenAIRE. È possibile inserire, o importare direttamente dalle banche dati previste, le informazioni descrittive del documento e anche allegare, ove consentito dalla normativa sul diritto d'autore, il testo completo della pubblicazione.

ENEA-IRIS Open Archive utilizza la piattaforma IRIS (Institutional Research Information System) sviluppata da CINECA.

PESCARINI, MASSIMO
 Distribuzione geografica
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Continente #
EU - Europa 3.994
NA - Nord America 3.354
AS - Asia 1.912
SA - Sud America 365
AF - Africa 78
Continente sconosciuto - Info sul continente non disponibili 18
OC - Oceania 3
Totale 9.724
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Nazione #
US - Stati Uniti d'America 3.140
RU - Federazione Russa 2.858
SG - Singapore 918
CN - Cina 569
BR - Brasile 327
GB - Regno Unito 323
SE - Svezia 289
CA - Canada 192
IT - Italia 173
DE - Germania 155
HK - Hong Kong 127
JP - Giappone 80
KR - Corea 70
VN - Vietnam 54
MA - Marocco 52
FR - Francia 40
FI - Finlandia 36
BE - Belgio 27
IN - India 23
NL - Olanda 21
ZA - Sudafrica 20
ES - Italia 19
PL - Polonia 18
EU - Europa 16
UA - Ucraina 15
AR - Argentina 14
MX - Messico 14
BD - Bangladesh 12
IQ - Iraq 12
TR - Turchia 11
PK - Pakistan 7
EC - Ecuador 6
CO - Colombia 5
ID - Indonesia 4
IR - Iran 4
CH - Svizzera 3
CL - Cile 3
IL - Israele 3
KE - Kenya 3
PS - Palestinian Territory 3
RO - Romania 3
VE - Venezuela 3
AL - Albania 2
AT - Austria 2
BG - Bulgaria 2
DO - Repubblica Dominicana 2
IE - Irlanda 2
KG - Kirghizistan 2
NZ - Nuova Zelanda 2
PA - Panama 2
PY - Paraguay 2
UZ - Uzbekistan 2
XK - ???statistics.table.value.countryCode.XK??? 2
AE - Emirati Arabi Uniti 1
AU - Australia 1
AZ - Azerbaigian 1
BO - Bolivia 1
CR - Costa Rica 1
DM - Dominica 1
DZ - Algeria 1
EE - Estonia 1
EG - Egitto 1
GR - Grecia 1
GY - Guiana 1
HN - Honduras 1
HU - Ungheria 1
JO - Giordania 1
KH - Cambogia 1
KW - Kuwait 1
KZ - Kazakistan 1
LB - Libano 1
LT - Lituania 1
LU - Lussemburgo 1
NI - Nicaragua 1
NP - Nepal 1
OM - Oman 1
PE - Perù 1
QA - Qatar 1
SI - Slovenia 1
SN - Senegal 1
SR - Suriname 1
SY - Repubblica araba siriana 1
UY - Uruguay 1
Totale 9.724
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Città #
Dallas 976
Moscow 670
Chandler 598
Singapore 447
Santa Clara 192
Toronto 175
Hefei 171
San Mateo 170
Southend 167
Ashburn 128
Hong Kong 126
Boardman 118
New York 116
Beijing 109
Columbus 58
Seoul 58
Berlin 57
Casablanca 48
The Dalles 48
Dong Ket 36
Falkenstein 36
São Paulo 36
Trenton 34
Helsinki 32
Council Bluffs 31
Washington 31
Los Angeles 30
Brussels 27
Las Vegas 23
Munich 20
Rome 20
Ann Arbor 19
Miami 19
Mountain View 18
Warsaw 18
Shanghai 17
Marseille 15
Zhengzhou 14
Guangzhou 12
Johannesburg 11
Rio de Janeiro 11
Boston 10
Denver 10
Redwood City 10
Hanoi 9
Montreal 9
Stockholm 9
Milan 8
Atlanta 7
Bologna 7
Brooklyn 7
Gatchina 7
Kyiv 7
London 7
Mexico City 7
Poplar 7
Tokyo 7
Amsterdam 6
Ankara 6
Frankfurt am Main 6
Hanover 6
Manaus 6
Mazzano Romano 6
Paris 6
Baghdad 5
Bruino 5
Changsha 5
Dhaka 5
Düsseldorf 5
Goiânia 5
Houston 5
Manchester 5
Phoenix 5
Porto Alegre 5
San Francisco 5
São Bernardo do Campo 5
Tampa 5
Cape Town 4
Charlotte 4
Chennai 4
Herzberg 4
Ho Chi Minh City 4
Lauterbourg 4
Nizhniy Novgorod 4
Sumaré 4
Bogotá 3
Borås 3
Brasília 3
Campinas 3
Curitiba 3
Islamabad 3
Londrina 3
Madrid 3
Magdeburg 3
Milwaukee 3
Mumbai 3
Nairobi 3
Naples 3
Natal 3
Orem 3
Totale 5.254
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Nome #
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 314
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report 273
A Review of the Activities of the Nuclear Data Center at ENEA 240
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 232
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 227
A Neutron Cross Section Evaluation for Th-232 in the En &l 20 MeV Energy Range 214
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 213
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code 210
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 209
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 204
Data Processing and Validation Needs of Group-Wise Working Cross Section Libraries for Nuclear Fission Reactor Shielding and Radiation Damage Applications 204
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 201
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 198
ENEA-Bologna Multi-Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry Applications 198
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications 190
ENEA-BOLOGNA PRODUCTION AND TESTING OF JEF-2.2 MULTI-GROUP CROSS SECTION LIBRARIES FOR NUCLEAR FISSION APPLICATIONS 189
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705 188
A Neutron Cross Section Evaluation for 232Th in the En <20 MeV Energy Range 180
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 180
ENEA-Bologna 2007 Revision of the SCAMPI (ORNL) Nuclear Data Processing System 179
ENEA-BOLOGNA NUCLEAR DATA CENTRE - A Summary of the Main Objectives Achieved in the Period 1997-2001 177
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 169
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 167
JENDL-3.1 and ENDF/B VI Iron Validation on the (H2O/FE) PCA-REPLICA Shielding Benchmark 165
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results 163
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 158
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations 158
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 157
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment 156
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 154
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 151
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 149
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment 149
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data 149
VITJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 148
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format 148
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 148
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code 146
JENDL-3.1 Iron Validation on the PCA-Replica (H2O/FE), Shielding Benchmark Experiment - JEFF/DOC-703 145
MATJEFF31.BOLIB - A JEFF-3.1 Multi-Group Coupled (199 n + 42gamma) Cross Section Library in MATXS Format for Nuclear Fission Applications 145
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment 145
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 145
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations 144
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code 143
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 143
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method 143
VITJEF22.BOLIB - A JEF-2.2 MULTIGROUP COUPLED (199 n + 42 gamma) CROSS SECTION LIBRARY IN AMPX FORMAT FOR NUCLEAR FISSION APPLICATIONS 142
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 142
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment 142
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 141
Status of the JEFF Nuclear Data Library 140
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 140
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 136
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 136
MATJEF22.BOLIB - A JEF-2.2 MULTIGROUP COUPLED (199 n + 42 gamma) CROSS SECTION LIBRARY IN MATXS FORMAT FOR NUCLEAR FISSION APPLICATIONS 134
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment 132
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra 131
Totale 9.724
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Categoria #
all - tutte 41.274
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 41.274
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021285 0 0 0 0 0 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
2024/20254.153 7 178 58 45 247 73 154 151 191 148 1.195 1.706
2025/20262.782 463 947 624 375 279 94 0 0 0 0 0 0
Totale 9.724