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.

ORSI, ROBERTO
 Distribuzione geografica
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Continente #
NA - Nord America 9.206
EU - Europa 5.985
AS - Asia 3.292
SA - Sud America 493
AF - Africa 116
Continente sconosciuto - Info sul continente non disponibili 24
OC - Oceania 9
Totale 19.125
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Nazione #
US - Stati Uniti d'America 8.875
RU - Federazione Russa 4.062
SG - Singapore 1.574
CN - Cina 931
GB - Regno Unito 490
BR - Brasile 437
SE - Svezia 406
CA - Canada 297
IT - Italia 254
DE - Germania 231
HK - Hong Kong 163
FR - Francia 160
NL - Olanda 157
VN - Vietnam 154
JP - Giappone 133
KR - Corea 94
MA - Marocco 70
IN - India 65
FI - Finlandia 52
BD - Bangladesh 39
BE - Belgio 37
PL - Polonia 33
ES - Italia 26
TR - Turchia 23
UA - Ucraina 23
ZA - Sudafrica 22
AR - Argentina 21
MX - Messico 20
EU - Europa 19
IQ - Iraq 19
PK - Pakistan 13
ID - Indonesia 12
IE - Irlanda 9
IR - Iran 9
EC - Ecuador 8
CH - Svizzera 7
SA - Arabia Saudita 7
CZ - Repubblica Ceca 6
LT - Lituania 6
PE - Perù 6
AT - Austria 5
AU - Australia 5
CL - Cile 5
IL - Israele 5
JO - Giordania 5
MY - Malesia 5
PH - Filippine 5
RO - Romania 5
UZ - Uzbekistan 5
VE - Venezuela 5
AL - Albania 4
DZ - Algeria 4
NP - Nepal 4
PA - Panama 4
PS - Palestinian Territory 4
PY - Paraguay 4
TW - Taiwan 4
CO - Colombia 3
EG - Egitto 3
KZ - Kazakistan 3
NZ - Nuova Zelanda 3
TN - Tunisia 3
AE - Emirati Arabi Uniti 2
AO - Angola 2
AZ - Azerbaigian 2
BO - Bolivia 2
BY - Bielorussia 2
CI - Costa d'Avorio 2
KE - Kenya 2
NI - Nicaragua 2
OM - Oman 2
TH - Thailandia 2
AM - Armenia 1
BB - Barbados 1
BG - Bulgaria 1
BS - Bahamas 1
DM - Dominica 1
DO - Repubblica Dominicana 1
ET - Etiopia 1
GE - Georgia 1
GR - Grecia 1
GY - Guiana 1
HN - Honduras 1
HR - Croazia 1
JM - Giamaica 1
KG - Kirghizistan 1
KH - Cambogia 1
KN - Saint Kitts e Nevis 1
KW - Kuwait 1
LB - Libano 1
LS - Lesotho 1
LU - Lussemburgo 1
LV - Lettonia 1
MK - Macedonia 1
MU - Mauritius 1
NO - Norvegia 1
PR - Porto Rico 1
PT - Portogallo 1
QA - Qatar 1
RE - Reunion 1
Totale 19.111
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Città #
Dallas 4.333
Moscow 948
Chandler 871
San Jose 692
Singapore 692
Ashburn 394
Santa Clara 297
Toronto 251
Hefei 249
San Mateo 248
Southend 240
Beijing 172
New York 171
Boardman 169
Council Bluffs 169
Hong Kong 152
Amsterdam 132
The Dalles 114
Columbus 95
Berlin 83
Seoul 83
Lauterbourg 74
Los Angeles 71
Trenton 67
Casablanca 64
Washington 47
Helsinki 45
Milan 45
Falkenstein 44
Ho Chi Minh City 41
São Paulo 41
Las Vegas 38
Brussels 37
Ann Arbor 36
Dong Ket 35
Hanoi 34
Warsaw 31
Munich 29
Miami 28
Marseille 27
Montreal 26
Guangzhou 25
Mountain View 25
Shanghai 25
Redwood City 23
Tokyo 23
Zhengzhou 23
Rome 22
Orem 21
Bologna 19
Chennai 19
Denver 19
Rio de Janeiro 19
Houston 18
Atlanta 17
Stockholm 17
London 16
Manchester 16
Brooklyn 14
Phoenix 13
Frankfurt am Main 12
Kyiv 11
Ankara 10
Changsha 10
Düsseldorf 10
Johannesburg 10
Mexico City 10
Naples 10
Poplar 10
Porto Alegre 10
Boston 9
Chicago 9
Da Nang 9
Dublin 9
Nuremberg 9
Paris 9
Shenzhen 9
Borås 8
Charlotte 8
Dhaka 8
Gatchina 8
San Francisco 8
Baghdad 7
Brasília 7
Manosque 7
Mumbai 7
St Petersburg 7
Curitiba 6
Hillsboro 6
Madrid 6
Tampa 6
Amman 5
Bruino 5
Buffalo 5
Goiânia 5
Haiphong 5
Islamabad 5
Istanbul 5
Manaus 5
Milwaukee 5
Totale 12.099
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Nome #
13th International Conference on Nuclear Engineering, Bejing, China, May 16-20, 2005 (ICONE 13-50746) WESTINGHOUSE AP1000 INTERNALS HEATING RATE DISTRIBUTION CALCULATION USING A 3D DETERMINISTIC TRANSPORT METHOD 3.438
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report 314
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis 261
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 260
BOT3P Version 5.4: A Pre/Post-Processor Code System for Transport Analysis 259
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 256
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 244
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis 241
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code 239
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 239
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 234
BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes 231
BOT3P Version 3.0: The ENEA Bologna Pre-Processors of the DORT, TORT, TWODANT, THREEDANT and MCNP Transport Codes and Post-Processors of DORT and TORT 230
ADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 229
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes 228
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 228
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 227
BOT3P Version 2.0: Two/Three-Dimensional Mesh Generator and Graphical Display of Geometry and Result for Deterministic Transport Codes 224
ADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 224
'TORT Solutions to the Three-Dimensional MOX neutron Transport Benchmarks' presentato a: 2003 ANS/ENS International Winter Meeting 'Nuclear Technology: Achieving Global Economic Growth While Safeguarding the Environment', November 16-20, 2003 New Orleans, Louisiana, USA 222
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis 219
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 219
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and its Implementation in BOT3P5.O 217
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications 216
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705 216
BOT3P Version 4.2: The ENEA Bologna Pre/Post-Processors of the DORT, TORT TWODANT, THREEDANT Transport Codes 214
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis 213
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 211
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 209
Recent Improvements to the Evaluated Data Files for Aluminium and Iron at the Nuclear Data Centre, Bologna 208
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses 202
A General Method to Conserve Mass in Complex Geometry Simulation on Mesh Grids and Its Implementation in BOT3P5.0 200
ADEFTA Version 2.0: A Program to Calcolate the Atomic Densities of a Compositional Model for Transport Analysis 198
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 196
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment 187
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 187
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results 185
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations 184
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations 180
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 179
H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code 179
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 178
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 177
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0 176
BOT3P: A Mesh Generation Software Package for the Transport Analysis Codes DORT, TORT, TWODANT, THREEDANT and MCNP 176
BOT3P-Bologna Transport Analysis Pre-Post-Processors Version 3.0 175
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark - Deterministic Analysis in Both Cartesian (X,Y,Z) and Cylindrical (R,Θ,Z) Geometries Using the TORT-3.2 3D Transport Code, the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and the BUGLE-96 Cross Section Libraries 175
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 174
DORT SOLUTIONS TO THE TWO-DIMENSIONAL CSG7MOX BENCHMARK PROBLEM 173
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P 172
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data 172
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code 171
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment 171
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 170
BOT3P- Bologna Transport Analysis Pre-Post-Processors Version 3.0 169
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format 169
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 168
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 168
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code 167
CATSM: A Pre-Processor Tool for Medical Applications 167
Quality Assurance on Evaluated Nuclear Data Files at the Nuclear Data Centre in Bologna 166
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment 165
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0 164
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 164
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure 164
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment 164
Tort Solutions to the Three-Dimensional MOX Benchmark, 3-D Extension C5G7MOX 163
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmarks 163
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 163
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method 162
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 160
Dort Solutions to the Two-Dimensional C5G7Mox Benchmark Problem 158
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX 158
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 156
Validation of the TORT Code, Distributed with the DOORS-3.2 Oak Ridge National Laboratory Package, on a Linux Platform with the Red-Hat Linux 9.0 Operative System 154
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0 153
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment 153
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra 151
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes 150
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes 149
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes 146
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P 144
BOT3P: A MESH GENERATION SOFTWARE PACKAGE FOR THE TRANSPORT ANALYSIS CODES DORT, TORT, TWODANT, TRREEDANT AND MCNP presentato a: INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS SNA 2003, PARIS, SEPTEMBER 22-24 2003 140
Totale 19.125
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Categoria #
all - tutte 70.383
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 70.383
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022826 0 251 27 42 116 25 5 224 24 6 39 67
2022/20231.585 106 319 115 209 80 282 4 145 228 33 38 26
2023/2024866 56 24 113 8 105 168 15 67 115 56 32 107
2024/20256.106 20 284 67 120 393 142 159 244 305 221 1.716 2.435
2025/20268.864 666 1.838 3.322 580 379 447 748 336 163 166 138 81
2026/2027189 66 123 0 0 0 0 0 0 0 0 0 0
Totale 19.125