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 2.605
EU - Europa 1.352
AS - Asia 615
SA - Sud America 20
Continente sconosciuto - Info sul continente non disponibili 19
OC - Oceania 7
AF - Africa 5
Totale 4.623
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Nazione #
US - Stati Uniti d'America 2.356
GB - Regno Unito 430
SE - Svezia 347
CN - Cina 302
CA - Canada 247
SG - Singapore 173
DE - Germania 121
IT - Italia 112
RU - Federazione Russa 102
NL - Olanda 74
FI - Finlandia 45
FR - Francia 45
HK - Hong Kong 39
BE - Belgio 35
VN - Vietnam 35
BR - Brasile 20
EU - Europa 19
IN - India 19
JP - Giappone 15
UA - Ucraina 14
KR - Corea 9
ES - Italia 6
IE - Irlanda 6
CZ - Repubblica Ceca 5
AU - Australia 4
RO - Romania 4
CH - Svizzera 3
NZ - Nuova Zelanda 3
PK - Pakistan 3
CI - Costa d'Avorio 2
ID - Indonesia 2
IQ - Iraq 2
IR - Iran 2
MY - Malesia 2
SA - Arabia Saudita 2
TH - Thailandia 2
ZA - Sudafrica 2
AL - Albania 1
AM - Armenia 1
AT - Austria 1
BD - Bangladesh 1
IL - Israele 1
KW - Kuwait 1
KZ - Kazakistan 1
MA - Marocco 1
MX - Messico 1
NO - Norvegia 1
PA - Panama 1
PH - Filippine 1
TR - Turchia 1
TW - Taiwan 1
Totale 4.623
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Città #
Chandler 871
San Mateo 248
Toronto 242
Southend 240
Boardman 169
New York 129
Santa Clara 99
Ashburn 90
Berlin 83
Singapore 71
Trenton 67
Amsterdam 65
Beijing 47
Washington 46
Helsinki 43
Ann Arbor 36
Brussels 35
Dong Ket 35
Las Vegas 35
Hong Kong 34
Marseille 26
Mountain View 25
Miami 23
Redwood City 23
Zhengzhou 19
Guangzhou 16
Bologna 11
Moscow 11
Borås 8
Changsha 8
Kyiv 8
Milan 8
Shanghai 7
Dublin 6
Los Angeles 6
Paris 6
Rome 6
Bruino 5
Gatchina 5
Munich 5
Shenzhen 5
St Petersburg 5
Tampa 5
Dallas 4
Hanover 4
Herzberg 4
Horia 4
Ladson 4
Montreal 4
Rockville 4
West Jordan 4
Fremont 3
Grottammare 3
Magdeburg 3
Abidjan 2
Auckland 2
Bangalore 2
Barceloneta 2
Clifton 2
Columbia 2
Des Moines 2
Hopkins 2
Islamabad 2
Madrid 2
Monroeville 2
Mosul 2
Osaka 2
Perm 2
Povegliano Veronese 2
Saint-Fons 2
Semarang 2
Seongdong-gu 2
Sydney 2
Torrelavega 2
Turin 2
Xian 2
Aktau 1
Avelar 1
Bad Schoenborn 1
Bassano del Grappa 1
Beaumont 1
Boa Viagem 1
Bourg-la-Reine 1
Brisbane 1
Brooklyn 1
Bursa 1
Cambridge 1
Casape 1
Caxias do Sul 1
Chicago 1
Cleveland 1
Criciúma 1
Danbury 1
Delhi 1
Fairfield 1
Forest City 1
Foshan 1
Frankfurt am Main 1
Frosinone 1
Gold Coast 1
Totale 3.041
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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 167
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report 100
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis 93
BOT3P Version 5.4: A Pre/Post-Processor Code System for Transport Analysis 89
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 82
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 78
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 74
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses 71
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 67
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis 66
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 65
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 64
BOT3P: A Mesh Generation Software Package for the Transport Analysis Codes DORT, TORT, TWODANT, THREEDANT and MCNP 64
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes 64
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 64
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis 63
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 63
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 63
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 62
'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 62
ADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 62
BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes 61
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis 61
H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code 60
BOT3P Version 2.0: Two/Three-Dimensional Mesh Generator and Graphical Display of Geometry and Result for Deterministic Transport Codes 59
ADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 59
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment 58
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 58
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format 58
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 58
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations 58
Recent Improvements to the Evaluated Data Files for Aluminium and Iron at the Nuclear Data Centre, Bologna 58
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0 56
Dort Solutions to the Two-Dimensional C5G7Mox Benchmark Problem 56
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code 56
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data 56
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and its Implementation in BOT3P5.O 53
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 53
CATSM: A Pre-Processor Tool for Medical Applications 53
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 53
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment 53
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 53
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 52
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 52
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705 52
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P 51
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 51
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 51
BOT3P- Bologna Transport Analysis Pre-Post-Processors Version 3.0 50
Quality Assurance on Evaluated Nuclear Data Files at the Nuclear Data Centre in Bologna 50
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications 50
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code 49
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmarks 49
BOT3P Version 4.2: The ENEA Bologna Pre/Post-Processors of the DORT, TORT TWODANT, THREEDANT Transport Codes 49
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method 49
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code 48
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 48
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations 48
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results 47
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment 47
Tort Solutions to the Three-Dimensional MOX Benchmark, 3-D Extension C5G7MOX 46
ADEFTA Version 2.0: A Program to Calcolate the Atomic Densities of a Compositional Model for Transport Analysis 46
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0 46
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 46
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure 46
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 46
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 45
BOT3P-Bologna Transport Analysis Pre-Post-Processors Version 3.0 44
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra 44
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment 44
A General Method to Conserve Mass in Complex Geometry Simulation on Mesh Grids and Its Implementation in BOT3P5.0 43
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P 42
DORT SOLUTIONS TO THE TWO-DIMENSIONAL CSG7MOX BENCHMARK PROBLEM 42
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 42
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX 41
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 41
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes 38
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 38
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 38
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment 38
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0 36
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes 36
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes 33
Totale 4.627
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Categoria #
all - tutte 33.430
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 33.430
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202057 0 0 0 0 6 10 8 6 12 13 2 0
2020/2021620 3 6 9 11 192 0 6 55 31 25 243 39
2021/2022838 12 251 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
2024/2025661 20 284 67 120 170 0 0 0 0 0 0 0
Totale 4.627