statistiche ricercatore

ORSI, ROBERTO

Distribuzione geografica

Continente	#
NA - Nord America	8.916
EU - Europa	5.910
AS - Asia	3.252
SA - Sud America	484
AF - Africa	115
Continente sconosciuto - Info sul continente non disponibili	20
OC - Oceania	9
Totale	18.706

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Nazione	#
US - Stati Uniti d'America	8.592
RU - Federazione Russa	4.062
SG - Singapore	1.570
CN - Cina	915
GB - Regno Unito	489
BR - Brasile	432
SE - Svezia	385
CA - Canada	295
DE - Germania	231
IT - Italia	221
HK - Hong Kong	163
NL - Olanda	157
VN - Vietnam	154
FR - Francia	152
JP - Giappone	133
KR - Corea	94
MA - Marocco	70
IN - India	65
FI - Finlandia	52
BE - Belgio	37
PL - Polonia	32
TR - Turchia	23
ES - Italia	22
UA - Ucraina	22
ZA - Sudafrica	22
AR - Argentina	20
MX - Messico	20
BD - Bangladesh	19
EU - Europa	19
IQ - Iraq	19
PK - Pakistan	13
ID - Indonesia	12
IR - Iran	9
IE - Irlanda	8
EC - Ecuador	7
SA - Arabia Saudita	7
LT - Lituania	6
AT - Austria	5
AU - Australia	5
CH - Svizzera	5
CZ - Repubblica Ceca	5
IL - Israele	5
JO - Giordania	5
MY - Malesia	5
PE - Perù	5
PH - Filippine	5
RO - Romania	5
UZ - Uzbekistan	5
VE - Venezuela	5
AL - Albania	4
CL - Cile	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
CI - Costa d'Avorio	2
KE - Kenya	2
NI - Nicaragua	2
OM - Oman	2
TH - Thailandia	2
AM - Armenia	1
BY - Bielorussia	1
DM - Dominica	1
DO - Repubblica Dominicana	1
ET - Etiopia	1
GE - Georgia	1
GR - Grecia	1
GY - Guiana	1
HR - Croazia	1
KG - Kirghizistan	1
KH - Cambogia	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
RS - Serbia	1
SI - Slovenia	1
SN - Senegal	1
TJ - Tagikistan	1
TO - Tonga	1
UY - Uruguay	1
Totale	18.703

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Città	#
Dallas	4.327
Moscow	948
Chandler	871
Singapore	692
San Jose	673
Ashburn	377
Santa Clara	289
Toronto	251
Hefei	249
San Mateo	248
Southend	240
Beijing	172
New York	170
Boardman	169
Hong Kong	152
Amsterdam	132
The Dalles	113
Columbus	95
Berlin	83
Seoul	83
Lauterbourg	74
Trenton	67
Los Angeles	66
Casablanca	64
Washington	47
Helsinki	45
Falkenstein	44
Milan	42
Ho Chi Minh City	41
São Paulo	40
Brussels	37
Ann Arbor	36
Las Vegas	36
Dong Ket	35
Hanoi	34
Warsaw	30
Munich	29
Marseille	27
Miami	27
Montreal	26
Council Bluffs	25
Guangzhou	25
Mountain View	25
Shanghai	25
Redwood City	23
Tokyo	23
Zhengzhou	23
Orem	21
Rome	21
Chennai	19
Denver	19
Rio de Janeiro	19
Stockholm	17
Bologna	16
Manchester	16
Atlanta	15
London	15
Brooklyn	14
Houston	14
Frankfurt am Main	12
Kyiv	11
Ankara	10
Changsha	10
Düsseldorf	10
Johannesburg	10
Mexico City	10
Phoenix	10
Poplar	10
Porto Alegre	10
Boston	9
Da Nang	9
Nuremberg	9
Paris	9
Borås	8
Charlotte	8
Chicago	8
Dhaka	8
Dublin	8
Gatchina	8
Shenzhen	8
Baghdad	7
Brasília	7
Mumbai	7
St Petersburg	7
Curitiba	6
Hillsboro	6
Naples	6
San Francisco	6
Amman	5
Bruino	5
Buffalo	5
Haiphong	5
Islamabad	5
Istanbul	5
Madrid	5
Manaus	5
Mosul	5
Nizhniy Novgorod	5
Quito	5
Salvador	5
Totale	11.863

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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	3.430
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report	301
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis	258
BOT3P Version 5.4: A Pre/Post-Processor Code System for Transport Analysis	256
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	253
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	252
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	240
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code	232
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	231
BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes	228
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	227
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	225
ADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	225
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	222
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	222
BOT3P Version 2.0: Two/Three-Dimensional Mesh Generator and Graphical Display of Geometry and Result for Deterministic Transport Codes	221
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis	221
ADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	219
'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	216
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis	216
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	216
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes	215
BOT3P Version 4.2: The ENEA Bologna Pre/Post-Processors of the DORT, TORT TWODANT, THREEDANT Transport Codes	212
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and its Implementation in BOT3P5.O	211
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications	211
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis	209
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705	208
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	207
Recent Improvements to the Evaluated Data Files for Aluminium and Iron at the Nuclear Data Centre, Bologna	205
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses	195
A General Method to Conserve Mass in Complex Geometry Simulation on Mesh Grids and Its Implementation in BOT3P5.0	194
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code	193
ADEFTA Version 2.0: A Program to Calcolate the Atomic Densities of a Compositional Model for Transport Analysis	192
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment	184
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results	182
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment	180
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	180
H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code	177
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	176
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations	175
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications	175
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0	173
BOT3P: A Mesh Generation Software Package for the Transport Analysis Codes DORT, TORT, TWODANT, THREEDANT and MCNP	172
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications	172
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	172
BOT3P-Bologna Transport Analysis Pre-Post-Processors Version 3.0	171
DORT SOLUTIONS TO THE TWO-DIMENSIONAL CSG7MOX BENCHMARK PROBLEM	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
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	169
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data	169
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations	169
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code	168
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment	168
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format	167
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment	167
CATSM: A Pre-Processor Tool for Medical Applications	166
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code	165
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code	164
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 broad-group libraries on the PCA-Replica (H2O/Fe) neutron shielding benchmark experiment	163
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations	163
BOT3P- Bologna Transport Analysis Pre-Post-Processors Version 3.0	162
Quality Assurance on Evaluated Nuclear Data Files at the Nuclear Data Centre in Bologna	162
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	162
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment	162
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure	161
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmarks	159
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	159
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	158
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method	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
Dort Solutions to the Two-Dimensional C5G7Mox Benchmark Problem	156
Tort Solutions to the Three-Dimensional MOX Benchmark, 3-D Extension C5G7MOX	156
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX	156
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	152
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment	151
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	150
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra	149
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	148
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	145
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	144
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes	139
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	137
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	135
Totale	18.710

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Categoria	#
all - tutte	66.148
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	66.148

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	307	0	0	0	0	0	0	0	0	0	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	8.638	666	1.838	3.322	580	379	447	748	336	163	159	0	0
Totale													18.710