statistiche ricercatore

ORSI, ROBERTO

Distribuzione geografica

Continente	#
NA - Nord America	2.873
EU - Europa	1.617
AS - Asia	946
SA - Sud America	286
Continente sconosciuto - Info sul continente non disponibili	20
AF - Africa	17
OC - Oceania	7
Totale	5.766

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Nazione	#
US - Stati Uniti d'America	2.614
GB - Regno Unito	436
SG - Singapore	358
SE - Svezia	347
CN - Cina	319
BR - Brasile	266
CA - Canada	252
DE - Germania	190
IT - Italia	190
NL - Olanda	141
RU - Federazione Russa	119
HK - Hong Kong	112
FR - Francia	61
FI - Finlandia	46
VN - Vietnam	37
BE - Belgio	36
JP - Giappone	28
IN - India	20
EU - Europa	19
UA - Ucraina	17
IQ - Iraq	10
KR - Corea	9
TR - Turchia	8
IE - Irlanda	7
PK - Pakistan	7
ZA - Sudafrica	7
AR - Argentina	6
ES - Italia	6
CZ - Repubblica Ceca	5
AU - Australia	4
CH - Svizzera	4
IR - Iran	4
MA - Marocco	4
RO - Romania	4
BD - Bangladesh	3
ID - Indonesia	3
IL - Israele	3
MX - Messico	3
NZ - Nuova Zelanda	3
SA - Arabia Saudita	3
AL - Albania	2
AT - Austria	2
AZ - Azerbaigian	2
CI - Costa d'Avorio	2
CL - Cile	2
CO - Colombia	2
EC - Ecuador	2
JO - Giordania	2
KZ - Kazakistan	2
MY - Malesia	2
NI - Nicaragua	2
NP - Nepal	2
OM - Oman	2
PA - Panama	2
PE - Perù	2
PH - Filippine	2
PY - Paraguay	2
TH - Thailandia	2
TN - Tunisia	2
AM - Armenia	1
BO - Bolivia	1
BY - Bielorussia	1
DZ - Algeria	1
GY - Guiana	1
KG - Kirghizistan	1
KW - Kuwait	1
LT - Lituania	1
LU - Lussemburgo	1
NO - Norvegia	1
PS - Palestinian Territory	1
SN - Senegal	1
TW - Taiwan	1
UY - Uruguay	1
UZ - Uzbekistan	1
VE - Venezuela	1
XK - ???statistics.table.value.countryCode.XK???	1
Totale	5.766

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Città	#
Chandler	871
Santa Clara	264
San Mateo	248
Toronto	245
Southend	240
Boardman	169
New York	129
Amsterdam	120
Hong Kong	106
Singapore	97
Ashburn	91
Berlin	83
Trenton	67
Beijing	47
Washington	46
Falkenstein	44
Helsinki	44
Milan	40
Ann Arbor	36
Brussels	36
Dong Ket	35
Las Vegas	35
Marseille	26
Council Bluffs	25
Mountain View	25
Miami	23
Redwood City	23
The Dalles	22
Los Angeles	21
São Paulo	20
Zhengzhou	20
Guangzhou	16
Moscow	16
Rome	13
Bologna	12
Shanghai	12
Rio de Janeiro	11
Düsseldorf	10
Borås	8
Changsha	8
Frankfurt am Main	8
Kyiv	8
Nuremberg	8
Dublin	7
Lauterbourg	7
Gatchina	6
Paris	6
St Petersburg	6
Bruino	5
Munich	5
Shenzhen	5
Tampa	5
Tokyo	5
Baghdad	4
Brasília	4
Curitiba	4
Dallas	4
Florence	4
Hanover	4
Herzberg	4
Horia	4
Ladson	4
Montreal	4
Naples	4
Rockville	4
Santa Luzia	4
West Jordan	4
Fremont	3
Goiânia	3
Grottammare	3
Magdeburg	3
Manaus	3
Mosul	3
Natal	3
Nizhniy Novgorod	3
Salvador	3
Turin	3
Abidjan	2
Amman	2
Aparecida de Goiânia	2
Araraquara	2
Araxá	2
Auckland	2
Baku	2
Bangalore	2
Barceloneta	2
Belo Horizonte	2
Camaçari	2
Canoas	2
Caratinga	2
Chicago	2
Clifton	2
Columbia	2
Des Moines	2
Dhaka	2
Frederico Westphalen	2
Guarulhos	2
Hopkins	2
Ijuí	2
Islamabad	2
Totale	3.617

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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	229
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report	137
B0T3P Version 5.3: A Pre/Post-Processor System for Transport Analysis	122
BOT3P Version 5.4: A Pre/Post-Processor Code System for Transport Analysis	102
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	98
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	97
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	92
ADEFTA Version 3.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	90
MCJEF22.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code	87
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	87
ADEFTA Version 4.1: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	86
H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses	85
BOT3P Version 2.0: Two/Three-Dimensional Mesh Generator and Graphical Display of Geometry and Result for Deterministic Transport Codes	84
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	82
BOT3P Version 4.0: The ENEA Bologna Pre/Post-Processors of the DORT, TORT, TWODANT, THREEDANT Transport Codes	82
BOT3P-Bologna Transport Analysis Pre-Post-Processors Version 3.0	79
Processing and Validation of JEFF-3.1.1 and ENDF/B-VII.0 Group-Wise Cross Section Libraries for Shielding Calculations	79
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	79
BOT3P Version 2.0: The ENEA Nuclear Data Centre Pre/Post-Processors of the DORT, TORT, TWODANT and THREEDANT Deterministic Transport Codes	78
BOT3P Version 5.2: A Pre/Post-Processor System for Transport Analysis	78
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	78
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	78
Automatic Generation of 3D Fine Mesh Geometries for the Analysis of the VENUS-3 Shielding Benchmark Experiment with the TORT Code	77
BOT3P Version 5.0: A Pre/Post-Processor System for Transport Analysis	77
'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	75
ADEFTA: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	74
CATSM: A Pre-Processor Tool for Medical Applications	73
ENEA-Bologna Production and Testing of JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	72
ENEA-Bologna Production and Testing or JEFF-3.1 Multi-Group Cross Section Libraries for Nuclear Fission Applications	72
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	72
Recent Improvements to the Evaluated Data Files for Aluminium and Iron at the Nuclear Data Centre, Bologna	72
BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis	71
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment	70
BOT3P: A Mesh Generation Software Package for the Transport Analysis Codes DORT, TORT, TWODANT, THREEDANT and MCNP	69
BOT3P Version 4.2: The ENEA Bologna Pre/Post-Processors of the DORT, TORT TWODANT, THREEDANT Transport Codes	68
VITENDF70.BOLIB - An ENDF/B- VII.O Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format	67
ENDF/B-VI Multi-Temperature Neutron Library for MCNP JEFF/DOC-705	67
ADEFTA Version 4.0: A Program to Calculate the Atomic Densities of a Compositional Model for Transport Analysis	66
H.B. Robinson-2 pressure vessel dosimetry benchmark: Deterministic three-dimensional analysis with the TORT transport code	66
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0	65
A General Method of Conserving Mass in Complex Geometry Simulations on Mesh Grids and its Implementation in BOT3P5.O	65
ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment	65
DORT SOLUTIONS TO THE TWO-DIMENSIONAL CSG7MOX BENCHMARK PROBLEM	65
VITJEFF32.BOLIB - An ENEA-Bologna Fine-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format Based on JEFF-3.2 Data	65
ENEA-BOLOGNA Production and Testing of JEF-2.2 Multi-GroupCross Section Libraries for Nuclear Fission Applications	63
Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Shielding Benchmark Experiment - Preliminary Results	63
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	63
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	63
Dort Solutions to the Two-Dimensional C5G7Mox Benchmark Problem	62
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	62
VITJEFF32.BOLIB - A JEFF-3.2 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications	60
MCB6.BOLIB - An ENDF/B-VI Release 3 Cross Section Library for the MCNP Monte Carlo Code	59
Preliminary Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment	59
Tort Solutions to the Three-Dimensional MOX Benchmark, 3-D Extension C5G7MOX	58
BOT3P- Bologna Transport Analysis Pre-Post-Processors Version 3.0	58
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and BUGLE-96 Cross Section Libraries on the Iron-88 Neutron Shielding Benchmark Experiment	58
WESTINGHOUSE AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method	58
VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations	58
MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code	57
VITJEFF311.BOLIB - A JEFF-3.1.1 Multi-Group Coupled (199 n + 42 γ) Cross Section Library in AMPX Format for Nuclear Fission Applications	57
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmarks	56
Quality Assurance on Evaluated Nuclear Data Files at the Nuclear Data Centre in Bologna	56
ADEFTA Version 2.0: A Program to Calcolate the Atomic Densities of a Compositional Model for Transport Analysis	56
Dosimetry Cross Section Processing from IRDF-2002 in the BUGLE-96 (47 n) Neutron Group Structure	55
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	54
A General Method to Conserve Mass in Complex Geometry Simulation on Mesh Grids and Its Implementation in BOT3P5.0	54
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7 Broad-Group Libraries on the PCA-Replica (H2O/Fe) Neutron Shielding Benchmark Experiment	54
Validation of the BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-96 Cross Section Libraries on the PCA-Replica (Water/Iron) Neutron Shielding Benchmark Experiment	54
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations	54
IRDF-2002 Dosimetry Cross Section Processing in the BUGLE-96 (47 n) Neutron Group Structure Using Flat and Updated Problem Dependent Neutron Spectra	53
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	53
MCJEF22NEA.BOLIB - A JEF-2.2 Cross Section Library for the MCNP Monte Carlo Code	52
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX	51
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	51
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	50
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	49
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	49
BOT3P: A Mesh Generation Software Package for Transport Analysis with Deterministic and Monte Carlo Codes	49
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P	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
BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0	46
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	43
The ENEA-Bologna Pre-Post-Processor Package BOT3P for the DORT and TORT Transport Codes	37
Totale	5.770

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Categoria	#
all - tutte	38.393
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	38.393

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	15	0	0	0	0	0	0	0	0	0	13	2	0
2020/2021	620	3	6	9	11	192	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	1.804	20	284	67	120	393	142	159	244	305	70	0	0
Totale													5.770

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s_.*	plu.mx	sessione	recupero grafico citazioni sociali da plumx
A_.*	core.ac.uk	7 giorni	recupero pubblicazioni consigliate per il pannello core-recommander
GS_.*	gstatic.com	richiesta http	visualizza grafico citazioni
CC_.*	creativecommons.org	richiesta http	visualizza licenza bitstream