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 2.388
EU - Europa 1.155
AS - Asia 269
Continente sconosciuto - Info sul continente non disponibili 19
SA - Sud America 8
OC - Oceania 6
AF - Africa 4
Totale 3.849
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Nazione #
US - Stati Uniti d'America 2.141
GB - Regno Unito 429
SE - Svezia 347
CA - Canada 247
CN - Cina 144
DE - Germania 115
IT - Italia 91
FR - Francia 44
FI - Finlandia 43
HK - Hong Kong 37
BE - Belgio 35
VN - Vietnam 35
EU - Europa 19
IN - India 18
JP - Giappone 15
UA - Ucraina 12
RU - Federazione Russa 10
NL - Olanda 9
BR - Brasile 8
IE - Irlanda 5
AU - Australia 4
CZ - Repubblica Ceca 4
ES - Italia 4
RO - Romania 4
SG - Singapore 4
CH - Svizzera 3
PK - Pakistan 3
CI - Costa d'Avorio 2
ID - Indonesia 2
IQ - Iraq 2
IR - Iran 2
KR - Corea 2
NZ - Nuova Zelanda 2
SA - Arabia Saudita 2
ZA - Sudafrica 2
MY - Malesia 1
TH - Thailandia 1
TW - Taiwan 1
Totale 3.849
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Città #
Chandler 871
San Mateo 248
Toronto 242
Southend 240
New York 122
Ashburn 87
Berlin 83
Boardman 82
Trenton 67
Beijing 45
Washington 45
Helsinki 41
Ann Arbor 36
Brussels 35
Dong Ket 35
Las Vegas 35
Hong Kong 34
Marseille 26
Mountain View 25
Redwood City 23
Zhengzhou 18
Bologna 9
Borås 8
Changsha 8
Shanghai 7
Kyiv 6
Miami 6
Paris 6
Dublin 5
Los Angeles 5
Rome 5
Tampa 5
Dallas 4
Guangzhou 4
Hanover 4
Herzberg 4
Horia 4
Ladson 4
Montreal 4
Moscow 4
Rockville 4
Santa Clara 4
West Jordan 4
Fremont 3
Grottammare 3
Magdeburg 3
Abidjan 2
Bangalore 2
Barceloneta 2
Columbia 2
Des Moines 2
Hopkins 2
Islamabad 2
Monroeville 2
Mosul 2
Osaka 2
Povegliano Veronese 2
Saint-Fons 2
Semarang 2
Sydney 2
Torrelavega 2
Xian 2
Auckland 1
Bad Schoenborn 1
Bassano del Grappa 1
Beaumont 1
Brisbane 1
Brooklyn 1
Cambridge 1
Casape 1
Chicago 1
Cleveland 1
Danbury 1
Fairfield 1
Frankfurt am Main 1
Frosinone 1
Gold Coast 1
Gwanak-gu 1
Hangyang 1
Hounslow 1
Huizen 1
Ibra 1
Iglesias 1
Irkutsk 1
Kuala Lumpur 1
Lausanne 1
Magenta 1
Manchester 1
Mareno Di Piave 1
Martins Ferry 1
Mazzano Romano 1
Monterotondo 1
Montopoli in Val d'Arno 1
Napoli 1
Omsk 1
Prague 1
Ravenna 1
Redmond 1
San Jose 1
San Pietro in Casale 1
Totale 2.633
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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 91
BOT3P Version 5.4: A Pre/Post-Processor Code System for Transport Analysis 78
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 75
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report 68
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis 68
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 66
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses 66
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 64
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 59
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis 58
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 58
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 56
'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 55
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis 55
BOT3P: A Mesh Generation Software Package for the Transport Analysis Codes DORT, TORT, TWODANT, THREEDANT and MCNP 54
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 54
BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes 53
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis 53
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format 53
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 53
H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code 53
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment 52
Recent Improvements to the Evaluated Data Files for Aluminium and Iron at the Nuclear Data Centre, Bologna 52
BOT3P Version 2.0: Two/Three-Dimensional Mesh Generator and Graphical Display of Geometry and Result for Deterministic Transport Codes 51
ADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 51
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 51
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 50
Dort Solutions to the Two-Dimensional C5G7Mox Benchmark Problem 49
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 49
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data 49
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0 48
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 48
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code 48
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 48
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 47
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes 46
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment 46
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications 46
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and its Implementation in BOT3P5.O 45
Quality Assurance on Evaluated Nuclear Data Files at the Nuclear Data Centre in Bologna 45
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications 45
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 45
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705 45
BOT3P- Bologna Transport Analysis Pre-Post-Processors Version 3.0 44
ADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 44
CATSM: A Pre-Processor Tool for Medical Applications 44
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment 44
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method 44
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results 43
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications 43
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis 43
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code 42
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code 42
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmarks 42
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment 42
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code 42
BOT3P Version 4.2: The ENEA Bologna Pre/Post-Processors of the DORT, TORT TWODANT, THREEDANT Transport Codes 41
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 41
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations 40
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 40
BOT3P-Bologna Transport Analysis Pre-Post-Processors Version 3.0 39
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment 39
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 39
ADEFTA Version 2.0: A Program to Calcolate the Atomic Densities of a Compositional Model for Transport Analysis 38
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure 38
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
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0 37
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations 37
Tort Solutions to the Three-Dimensional MOX Benchmark, 3-D Extension C5G7MOX 36
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P 35
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX 35
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra 35
A General Method to Conserve Mass in Complex Geometry Simulation on Mesh Grids and Its Implementation in BOT3P5.0 35
DORT SOLUTIONS TO THE TWO-DIMENSIONAL CSG7MOX BENCHMARK PROBLEM 34
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 33
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes 31
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 31
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 31
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes 30
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0 29
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P 29
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment 29
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes 28
Totale 3.853
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Categoria #
all - tutte 26.377
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 26.377
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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
2023/2024753 56 24 113 8 105 168 15 67 115 56 26 0
Totale 3.853