statistiche ricercatore

ORSI, ROBERTO

Distribuzione geografica

Continente	#
NA - Nord America	7.887
EU - Europa	5.703
AS - Asia	2.826
SA - Sud America	446
AF - Africa	103
Continente sconosciuto - Info sul continente non disponibili	20
OC - Oceania	8
Totale	16.993

Salva come PNG Salva come JPEG

Nazione	#
US - Stati Uniti d'America	7.578
RU - Federazione Russa	4.055
SG - Singapore	1.372
CN - Cina	845
GB - Regno Unito	473
BR - Brasile	408
SE - Svezia	362
CA - Canada	287
DE - Germania	217
IT - Italia	205
HK - Hong Kong	152
NL - Olanda	149
JP - Giappone	129
KR - Corea	94
MA - Marocco	70
VN - Vietnam	67
FR - Francia	65
FI - Finlandia	51
IN - India	46
BE - Belgio	36
PL - Polonia	20
ZA - Sudafrica	20
EU - Europa	19
TR - Turchia	18
UA - Ucraina	18
ES - Italia	17
AR - Argentina	16
BD - Bangladesh	15
MX - Messico	15
IQ - Iraq	14
PK - Pakistan	11
IR - Iran	9
IE - Irlanda	7
CH - Svizzera	5
CZ - Repubblica Ceca	5
ID - Indonesia	5
SA - Arabia Saudita	5
AU - Australia	4
EC - Ecuador	4
IL - Israele	4
JO - Giordania	4
LT - Lituania	4
PS - Palestinian Territory	4
RO - Romania	4
TW - Taiwan	4
UZ - Uzbekistan	4
AT - Austria	3
CL - Cile	3
CO - Colombia	3
KZ - Kazakistan	3
NP - Nepal	3
NZ - Nuova Zelanda	3
PA - Panama	3
PE - Perù	3
PY - Paraguay	3
VE - Venezuela	3
AL - Albania	2
AZ - Azerbaigian	2
CI - Costa d'Avorio	2
DZ - Algeria	2
KE - Kenya	2
MY - Malesia	2
NI - Nicaragua	2
OM - Oman	2
PH - Filippine	2
TH - Thailandia	2
TN - Tunisia	2
AM - Armenia	1
AO - Angola	1
BO - Bolivia	1
BY - Bielorussia	1
DM - Dominica	1
DO - Repubblica Dominicana	1
EG - Egitto	1
ET - Etiopia	1
GE - Georgia	1
GR - Grecia	1
GY - Guiana	1
KG - Kirghizistan	1
KH - Cambogia	1
KW - Kuwait	1
LB - Libano	1
LU - Lussemburgo	1
MK - Macedonia	1
MU - Mauritius	1
NO - Norvegia	1
QA - Qatar	1
SN - Senegal	1
TJ - Tagikistan	1
TO - Tonga	1
UY - Uruguay	1
XK - ???statistics.table.value.countryCode.XK???	1
Totale	16.993

Salva come PNG Salva come JPEG

Città	#
Dallas	4.326
Moscow	948
Chandler	871
Singapore	641
Santa Clara	287
Toronto	251
Hefei	249
San Mateo	248
Southend	240
Ashburn	198
Beijing	172
Boardman	169
New York	158
Hong Kong	146
Amsterdam	126
The Dalles	98
Columbus	94
Berlin	83
Seoul	83
Trenton	67
Casablanca	64
Los Angeles	48
Washington	47
Falkenstein	44
Helsinki	44
Milan	40
Ann Arbor	36
Brussels	36
Las Vegas	36
São Paulo	36
Dong Ket	35
Munich	29
Marseille	26
Council Bluffs	25
Guangzhou	25
Miami	25
Mountain View	25
Shanghai	24
Redwood City	23
Zhengzhou	23
Tokyo	21
Montreal	20
Rome	20
Warsaw	18
Rio de Janeiro	16
Denver	15
Bologna	13
Hanoi	13
Stockholm	13
Brooklyn	12
Atlanta	11
Changsha	10
Düsseldorf	10
Houston	10
Johannesburg	10
London	10
Manchester	10
Porto Alegre	10
Ankara	9
Boston	9
Chennai	9
Frankfurt am Main	9
Ho Chi Minh City	9
Phoenix	9
Borås	8
Charlotte	8
Chicago	8
Gatchina	8
Kyiv	8
Mexico City	8
Nuremberg	8
Poplar	8
Dhaka	7
Dublin	7
Lauterbourg	7
Orem	7
Shenzhen	7
Brasília	6
Curitiba	6
Paris	6
San Francisco	6
St Petersburg	6
Baghdad	5
Bruino	5
Islamabad	5
Mumbai	5
Nizhniy Novgorod	5
Salvador	5
Tampa	5
Turku	5
Amman	4
Florence	4
Goiânia	4
Hanover	4
Herzberg	4
Horia	4
Ladson	4
Manaus	4
Milwaukee	4
Naples	4
Totale	10.651

Salva come PNG Salva come JPEG

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	3.403
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report	273
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis	234
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
BOT3P Version 5.4: A Pre/Post-Processor Code System for Transport Analysis	227
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
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
ADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	205
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	204
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	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
BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes	200
BOT3P Version 2.0: Two/Three-Dimensional Mesh Generator and Graphical Display of Geometry and Result for Deterministic Transport Codes	199
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	198
ADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	196
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis	196
'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	195
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis	194
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	194
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis	193
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes	192
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications	190
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705	188
BOT3P Version 4.2: The ENEA Bologna Pre/Post-Processors of the DORT, TORT TWODANT, THREEDANT Transport Codes	187
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	185
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and its Implementation in BOT3P5.O	183
Recent Improvements to the Evaluated Data Files for Aluminium and Iron at the Nuclear Data Centre, Bologna	183
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses	174
ADEFTA Version 2.0: A Program to Calcolate the Atomic Densities of a Compositional Model for Transport Analysis	172
A General Method to Conserve Mass in Complex Geometry Simulation on Mesh Grids and Its Implementation in BOT3P5.0	172
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
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results	163
H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code	160
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
BOT3P-Bologna Transport Analysis Pre-Post-Processors Version 3.0	156
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0	155
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
BOT3P: A Mesh Generation Software Package for the Transport Analysis Codes DORT, TORT, TWODANT, THREEDANT and MCNP	153
DORT SOLUTIONS TO THE TWO-DIMENSIONAL CSG7MOX BENCHMARK PROBLEM	151
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications	151
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	150
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	149
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
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
CATSM: A Pre-Processor Tool for Medical Applications	147
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code	146
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
BOT3P- Bologna Transport Analysis Pre-Post-Processors Version 3.0	144
Quality Assurance on Evaluated Nuclear Data Files at the Nuclear Data Centre in Bologna	144
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
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
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmarks	141
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
Tort Solutions to the Three-Dimensional MOX Benchmark, 3-D Extension C5G7MOX	140
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX	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
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure	138
Dort Solutions to the Two-Dimensional C5G7Mox Benchmark Problem	137
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	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
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	132
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment	132
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	131
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra	131
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	130
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	124
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes	121
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	120
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	116
Totale	16.997

Salva come PNG Salva come JPEG

Categoria	#
all - tutte	62.809
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	62.809

Salva come PNG Salva come JPEG

	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	399	0	0	0	0	0	0	6	55	31	25	243	39
2021/2022	838	12	251	27	42	116	25	5	224	24	6	39	67
2022/2023	1.585	106	319	115	209	80	282	4	145	228	33	38	26
2023/2024	866	56	24	113	8	105	168	15	67	115	56	32	107
2024/2025	6.106	20	284	67	120	393	142	159	244	305	221	1.716	2.435
2025/2026	6.925	666	1.838	3.322	580	379	140	0	0	0	0	0	0
Totale													16.997