statistiche ricercatore

ORSI, ROBERTO

Distribuzione geografica

Continente	#
NA - Nord America	9.760
EU - Europa	6.023
AS - Asia	3.322
SA - Sud America	540
AF - Africa	119
Continente sconosciuto - Info sul continente non disponibili	24
OC - Oceania	9
Totale	19.797

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Nazione	#
US - Stati Uniti d'America	9.410
RU - Federazione Russa	4.063
SG - Singapore	1.574
CN - Cina	931
GB - Regno Unito	503
BR - Brasile	452
SE - Svezia	406
CA - Canada	302
IT - Italia	266
DE - Germania	232
FR - Francia	165
HK - Hong Kong	164
VN - Vietnam	159
NL - Olanda	157
JP - Giappone	133
KR - Corea	94
MA - Marocco	70
IN - India	67
FI - Finlandia	52
BD - Bangladesh	40
BE - Belgio	38
PL - Polonia	34
ES - Italia	26
AR - Argentina	23
TR - Turchia	23
UA - Ucraina	23
MX - Messico	22
ZA - Sudafrica	22
EU - Europa	19
IQ - Iraq	19
CO - Colombia	18
EC - Ecuador	17
ID - Indonesia	16
PK - Pakistan	14
SA - Arabia Saudita	10
CZ - Repubblica Ceca	9
IE - Irlanda	9
IR - Iran	9
MY - Malesia	9
VE - Venezuela	9
PH - Filippine	8
CH - Svizzera	7
CL - Cile	6
LT - Lituania	6
PA - Panama	6
PE - Perù	6
AT - Austria	5
AU - Australia	5
IL - Israele	5
JO - Giordania	5
RO - Romania	5
UZ - Uzbekistan	5
AL - Albania	4
CR - Costa Rica	4
DZ - Algeria	4
KZ - Kazakistan	4
NP - Nepal	4
PS - Palestinian Territory	4
PY - Paraguay	4
TW - Taiwan	4
AE - Emirati Arabi Uniti	3
BO - Bolivia	3
CI - Costa d'Avorio	3
EG - Egitto	3
HN - Honduras	3
KE - Kenya	3
NZ - Nuova Zelanda	3
OM - Oman	3
TH - Thailandia	3
TN - Tunisia	3
AO - Angola	2
AZ - Azerbaigian	2
BS - Bahamas	2
BY - Bielorussia	2
JM - Giamaica	2
NI - Nicaragua	2
QA - Qatar	2
SC - Seychelles	2
AM - Armenia	1
BB - Barbados	1
BG - Bulgaria	1
BH - Bahrain	1
DM - Dominica	1
DO - Repubblica Dominicana	1
EE - Estonia	1
ET - Etiopia	1
GE - Georgia	1
GR - Grecia	1
GY - Guiana	1
HR - Croazia	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
Totale	19.778

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Città	#
Dallas	4.337
Moscow	948
Chandler	871
San Jose	694
Singapore	692
Ashburn	454
Santa Clara	299
Council Bluffs	273
Toronto	251
Hefei	249
San Mateo	248
Southend	240
Beijing	172
New York	171
Boardman	169
Hong Kong	152
Amsterdam	132
The Dalles	114
Columbus	96
Berlin	83
Seoul	83
Los Angeles	79
Lauterbourg	74
Phoenix	73
Trenton	68
Casablanca	64
Washington	48
Milan	47
Helsinki	45
Falkenstein	44
Ho Chi Minh City	44
São Paulo	41
Las Vegas	38
Brussels	37
Ann Arbor	36
North Tonawanda	36
Dong Ket	35
Hanoi	35
Manheim	33
Warsaw	31
Miami	29
Munich	29
Marseille	27
Montreal	26
Guangzhou	25
Mountain View	25
Shanghai	25
Rome	24
Redwood City	23
Tokyo	23
Zhengzhou	23
Atlanta	22
Orem	21
Rio de Janeiro	21
Chennai	20
Bologna	19
Denver	19
Houston	18
Stockholm	17
London	16
Manchester	16
Brooklyn	15
Brasília	12
Chicago	12
Frankfurt am Main	12
Kyiv	11
Ankara	10
Changsha	10
Da Nang	10
Düsseldorf	10
Johannesburg	10
Mexico City	10
Naples	10
Paris	10
Poplar	10
Porto Alegre	10
Bogotá	9
Boston	9
Charlotte	9
Dublin	9
Nuremberg	9
Shenzhen	9
Borås	8
Dhaka	8
Gatchina	8
San Francisco	8
Baghdad	7
Manosque	7
Mumbai	7
St Petersburg	7
Buffalo	6
Curitiba	6
Hillsboro	6
Madrid	6
Quito	6
Tampa	6
Amman	5
Bruino	5
Caracas	5
Goiânia	5
Totale	12.436

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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	3.456
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report	337
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	270
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis	267
BOT3P Version 5.4: A Pre/Post-Processor Code System for Transport Analysis	265
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	262
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis	251
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	250
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code	249
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	246
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	244
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	242
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	238
BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes	237
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes	237
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	235
BOT3P Version 2.0: Two/Three-Dimensional Mesh Generator and Graphical Display of Geometry and Result for Deterministic Transport Codes	234
ADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	233
ADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	233
'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	229
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	228
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and its Implementation in BOT3P5.O	227
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications	226
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis	226
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	222
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis	221
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705	220
BOT3P Version 4.2: The ENEA Bologna Pre/Post-Processors of the DORT, TORT TWODANT, THREEDANT Transport Codes	219
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	218
Recent Improvements to the Evaluated Data Files for Aluminium and Iron at the Nuclear Data Centre, Bologna	214
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses	210
A General Method to Conserve Mass in Complex Geometry Simulation on Mesh Grids and Its Implementation in BOT3P5.0	207
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code	205
ADEFTA Version 2.0: A Program to Calcolate the Atomic Densities of a Compositional Model for Transport Analysis	205
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations	195
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment	194
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment	194
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results	190
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations	190
H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code	188
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0	186
BOT3P-Bologna Transport Analysis Pre-Post-Processors Version 3.0	186
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications	185
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications	185
BOT3P: A Mesh Generation Software Package for the Transport Analysis Codes DORT, TORT, TWODANT, THREEDANT and MCNP	184
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	184
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	183
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code	181
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment	181
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment	179
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code	179
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	178
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data	178
BOT3P- Bologna Transport Analysis Pre-Post-Processors Version 3.0	177
DORT SOLUTIONS TO THE TWO-DIMENSIONAL CSG7MOX BENCHMARK PROBLEM	177
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	177
CATSM: A Pre-Processor Tool for Medical Applications	176
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format	176
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment	176
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code	174
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX	174
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations	173
Tort Solutions to the Three-Dimensional MOX Benchmark, 3-D Extension C5G7MOX	172
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure	172
Quality Assurance on Evaluated Nuclear Data Files at the Nuclear Data Centre in Bologna	171
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	171
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	171
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	171
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment	170
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method	170
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	169
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmarks	168
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	167
Dort Solutions to the Two-Dimensional C5G7Mox Benchmark Problem	162
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	162
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	160
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment	160
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	159
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra	158
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	157
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes	150
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	148
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	146
Totale	19.797

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Categoria	#
all - tutte	72.735
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	72.735

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	548	0	0	0	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	8.864	666	1.838	3.322	580	379	447	748	336	163	166	138	81
2026/2027	861	66	223	357	215	0	0	0	0	0	0	0	0
Totale													19.797