statistiche ricercatore

SAROTTO, MASSIMO

Distribuzione geografica

Continente	#
EU - Europa	6.660
NA - Nord America	6.108
AS - Asia	3.352
SA - Sud America	525
AF - Africa	132
Continente sconosciuto - Info sul continente non disponibili	13
OC - Oceania	11
Totale	16.801

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Nazione	#
US - Stati Uniti d'America	5.788
RU - Federazione Russa	3.921
SG - Singapore	1.570
CN - Cina	958
IT - Italia	896
GB - Regno Unito	451
BR - Brasile	449
DE - Germania	373
SE - Svezia	363
CA - Canada	274
FR - Francia	220
HK - Hong Kong	193
VN - Vietnam	145
JP - Giappone	113
AT - Austria	111
KR - Corea	88
IN - India	77
BE - Belgio	67
MA - Marocco	66
FI - Finlandia	51
BD - Bangladesh	39
NL - Olanda	39
CH - Svizzera	38
ES - Italia	32
MX - Messico	30
PL - Polonia	30
TW - Taiwan	30
AR - Argentina	27
ZA - Sudafrica	22
TR - Turchia	20
UA - Ucraina	15
UZ - Uzbekistan	15
IE - Irlanda	13
CO - Colombia	12
EC - Ecuador	12
EG - Egitto	12
KZ - Kazakistan	12
MY - Malesia	11
TN - Tunisia	11
EU - Europa	10
IQ - Iraq	10
PK - Pakistan	10
SA - Arabia Saudita	9
AU - Australia	8
DZ - Algeria	7
IR - Iran	7
LT - Lituania	7
VE - Venezuela	7
PH - Filippine	6
CL - Cile	5
DK - Danimarca	5
ID - Indonesia	5
JM - Giamaica	5
KG - Kirghizistan	5
LB - Libano	5
AL - Albania	4
AO - Angola	4
RO - Romania	4
AZ - Azerbaigian	3
CZ - Repubblica Ceca	3
DO - Repubblica Dominicana	3
HN - Honduras	3
KE - Kenya	3
LU - Lussemburgo	3
NP - Nepal	3
NZ - Nuova Zelanda	3
PE - Perù	3
PY - Paraguay	3
TT - Trinidad e Tobago	3
UY - Uruguay	3
A1 - Anonimo	2
AE - Emirati Arabi Uniti	2
AM - Armenia	2
BG - Bulgaria	2
BO - Bolivia	2
BY - Bielorussia	2
OM - Oman	2
SY - Repubblica araba siriana	2
TH - Thailandia	2
BA - Bosnia-Erzegovina	1
BH - Bahrain	1
BJ - Benin	1
BT - Bhutan	1
CI - Costa d'Avorio	1
CR - Costa Rica	1
EE - Estonia	1
GA - Gabon	1
GF - Guiana Francese	1
GT - Guatemala	1
GY - Guiana	1
HR - Croazia	1
HU - Ungheria	1
IL - Israele	1
JO - Giordania	1
KH - Cambogia	1
KW - Kuwait	1
LK - Sri Lanka	1
LV - Lettonia	1
MD - Moldavia	1
ME - Montenegro	1
Totale	16.792

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Città	#
Dallas	1.694
Moscow	916
Chandler	853
Singapore	760
San Jose	671
Ashburn	407
Santa Clara	259
Hefei	253
Toronto	229
San Mateo	222
Southend	208
Boardman	180
Beijing	174
Hong Kong	171
Rome	159
New York	131
The Dalles	108
Hamburg	99
Salerno	94
Seoul	82
Berlin	81
Vienna	74
Lauterbourg	72
Los Angeles	68
Milan	67
Turin	61
Columbus	60
Casablanca	59
Bologna	54
Brussels	50
Ho Chi Minh City	49
Falkenstein	46
Helsinki	42
Miami	38
Redwood City	37
São Paulo	37
Council Bluffs	35
Washington	35
Marseille	34
Orem	34
Ann Arbor	29
Mountain View	29
Nuremberg	27
Hanoi	26
Las Vegas	26
Munich	25
Tokyo	22
Warsaw	22
Belo Horizonte	21
Buffalo	21
Shanghai	19
Dhaka	18
Johannesburg	18
Montreal	18
Brooklyn	17
Frankfurt am Main	16
Manchester	15
Chennai	14
Guangzhou	14
London	14
Amsterdam	12
Denver	12
Taipei	12
Tashkent	12
Dresden	11
Paris	11
Phoenix	11
Poplar	11
Trenton	11
Atlanta	10
Boston	10
Cairo	10
Hillsboro	9
Jülich	9
Mexico City	9
Rio de Janeiro	9
San Francisco	9
Semey	9
Stockholm	9
Tong	9
Tortona	9
Bresso	8
Changsha	8
Chicago	8
Da Nang	8
Dublin	8
Genoa	8
Haiphong	8
Mol	8
Shenzhen	8
Turku	8
Brasília	7
Collecchio	7
Dong Ket	7
Guarulhos	7
Hsinchu	7
Inden	7
Lyon	7
Mumbai	7
New Delhi	7
Totale	9.471

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Nome	#
Deliverable D4.2 START core conceptual design	615
The current ALFRED core design	425
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	356
ELSY core design static, dynamic and safety parameters with the open square FA	343
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	292
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	275
Neutronic analyses of the ALFRED LEADER core with deterministic (ECCO / ERANOS) and Monte Carlo (Serpent) codes: comparison between macroscopic-group constants, shutdown systems worth and spatial-angular flux distributions	266
An epithermal facility for treating brain gliomas at the TAPIRO reactor	262
ELSY Open Square Fuel Assembly Design and Drawings	262
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment	261
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	256
EFIT -MgO/Pb Core Neutronic Preliminary Analysis	254
UOX-Fueled CLFR: core design	254
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length	249
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters	249
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core	235
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT	233
Analysis of MYRRHA/FASTEF to operate in a critical mode	231
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC	229
Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses	229
Deliverable D4.1 – START potential for fuel cycle services and options for START start-up core	227
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment	227
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	223
Design of an epithermal column for BNCT based on D-D fusion neutron facility	222
Critical core solutions for FASTEF (with hollow and solid pellets)	220
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	217
Neutronic analyses of the ALFRED LEADER core by deterministic (ERANOS) and Monte Carlo (Serpent) codes with JEFF-3.1 and ENDF/BVIII.0 libraries: comparison between flux and power spatial distributions in BoC/EoC nominal conditions	217
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project)	216
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	211
CDT/FASTEF Task 1.2 state of the art at the end of WP1	210
ELSY Neutronic Analysis: Status of the Open Square Design	210
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	207
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	207
The steady state neutronic modelling of the ALFRED core by the ERANOS deterministic code with an in-depth study on shutdown systems design bases and performances	207
Parametric MCNP analyses to address the design of a neutron collimator for high-flux compact DD sources to be used in cancer radiotherapy	206
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	204
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods	203
PDS-XADS Fuel Cycle Analysis by means of deterministic methods	195
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	194
LFR mock-up reactivity effects	194
LFR mock-up definition	192
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core	190
Analysis of MYRRHA-FASTEF to operate in a critical mode: first sketches for the critical layout (199 S/As) and main 'high flux task' decisions	190
Specification for the EFIT Core and Fuel Element	189
XT-ADS sensitivity analysis	189
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing	188
The current frozen design of the FASTEF critical core (151 SA): ERANOS model based on mechanical drawings (& referred to MCNPX). Some proposals for T2.2/D2.2: definition and simulation of the equilibrium sub-cycle core	185
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor	184
FASTEF design changes to operate in criticai mode	181
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level	180
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code	180
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): chosen approach and preliminary ERANOS results. Some proposals for the T2.2/D2.2 work plan	179
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases	176
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL	172
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor	170
Safety studies for the MYRRHA critical core with the SIMMER-III code	169
Shielding and activation calculations around the reactor core for the MYRRHA ADS design	169
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library)	169
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code	169
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	169
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code)	168
Preliminary FA/core design for MYRRHA/FASTEF	167
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data	165
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core	164
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)	162
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX	162
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code)	162
MYRRHA-FASTEF sub-critical core (30 wt. % EPu): Reactivity coefficients (ERANOS/JEFF3.1) and allowed levalo sub-critically at BoL. Last proposals for the T2.2/D2.2 work plan	161
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility	159
The 'complete' neutronic characterisation of the FASTEF critical core by ERANOS/JEFF3.1. Some proposals for Task 2.2: a possible approach for the sub-critical mode.	159
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods	158
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	157
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code	156
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods	153
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique	152
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode	151
Pre-fronzen FA and critical core for FASTEF	148
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations	148
The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code	147
The ERANOS model (based on mechanical drawings) of the current frozen MYRRHA-FASTEF critical core	146
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core	146
Totale	16.874

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Categoria	#
all - tutte	64.402
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	64.402

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	284	0	0	0	0	0	0	0	0	0	38	220	26
2021/2022	957	12	242	12	55	119	29	40	192	83	15	71	87
2022/2023	1.828	125	353	183	206	83	272	22	125	224	52	135	48
2023/2024	921	69	42	123	36	108	146	25	82	63	49	60	118
2024/2025	6.085	24	254	70	99	353	148	215	269	365	200	1.705	2.383
2025/2026	6.329	692	1.412	1.186	538	374	507	784	401	178	257	0	0
Totale													16.874