statistiche ricercatore

SAROTTO, MASSIMO

Distribuzione geografica

Continente	#
EU - Europa	6.358
NA - Nord America	5.050
AS - Asia	2.788
SA - Sud America	468
AF - Africa	116
Continente sconosciuto - Info sul continente non disponibili	13
OC - Oceania	11
Totale	14.804

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Nazione	#
US - Stati Uniti d'America	4.760
RU - Federazione Russa	3.918
SG - Singapore	1.333
CN - Cina	846
IT - Italia	774
GB - Regno Unito	430
BR - Brasile	416
SE - Svezia	361
DE - Germania	350
CA - Canada	259
HK - Hong Kong	179
FR - Francia	125
JP - Giappone	112
AT - Austria	110
KR - Corea	88
BE - Belgio	66
MA - Marocco	63
FI - Finlandia	50
IN - India	47
NL - Olanda	35
VN - Vietnam	33
BD - Bangladesh	32
CH - Svizzera	32
ES - Italia	28
TW - Taiwan	27
PL - Polonia	25
MX - Messico	24
AR - Argentina	19
TR - Turchia	17
ZA - Sudafrica	16
UA - Ucraina	15
EG - Egitto	12
KZ - Kazakistan	12
EU - Europa	10
IE - Irlanda	10
TN - Tunisia	9
AU - Australia	8
CO - Colombia	8
EC - Ecuador	8
UZ - Uzbekistan	8
DZ - Algeria	7
IR - Iran	7
PK - Pakistan	7
IQ - Iraq	6
LT - Lituania	6
DK - Danimarca	5
ID - Indonesia	4
KG - Kirghizistan	4
VE - Venezuela	4
AZ - Azerbaigian	3
CL - Cile	3
JM - Giamaica	3
LB - Libano	3
LU - Lussemburgo	3
MY - Malesia	3
NZ - Nuova Zelanda	3
PE - Perù	3
RO - Romania	3
A1 - Anonimo	2
AE - Emirati Arabi Uniti	2
AO - Angola	2
BG - Bulgaria	2
BO - Bolivia	2
BY - Bielorussia	2
HN - Honduras	2
KE - Kenya	2
OM - Oman	2
PH - Filippine	2
PY - Paraguay	2
SA - Arabia Saudita	2
SY - Repubblica araba siriana	2
UY - Uruguay	2
AM - Armenia	1
BA - Bosnia-Erzegovina	1
BJ - Benin	1
BT - Bhutan	1
CI - Costa d'Avorio	1
CZ - Repubblica Ceca	1
DO - Repubblica Dominicana	1
GA - Gabon	1
GT - Guatemala	1
GY - Guiana	1
HU - Ungheria	1
IL - Israele	1
JO - Giordania	1
KH - Cambogia	1
LV - Lettonia	1
MD - Moldavia	1
NP - Nepal	1
PS - Palestinian Territory	1
RS - Serbia	1
SI - Slovenia	1
SK - Slovacchia (Repubblica Slovacca)	1
SN - Senegal	1
XK - ???statistics.table.value.countryCode.XK???	1
ZW - Zimbabwe	1
Totale	14.804

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Città	#
Dallas	1.692
Moscow	916
Chandler	853
Singapore	675
Hefei	253
Santa Clara	253
Toronto	225
San Mateo	222
Ashburn	220
Southend	208
Boardman	180
Beijing	173
Hong Kong	159
New York	121
Hamburg	99
Salerno	94
The Dalles	88
Rome	84
Seoul	82
Berlin	81
Vienna	74
Columbus	60
Casablanca	58
Milan	57
Turin	57
Los Angeles	56
Brussels	49
Falkenstein	46
Helsinki	41
Bologna	40
Miami	38
Redwood City	37
Washington	35
Council Bluffs	33
Marseille	33
São Paulo	31
Ann Arbor	29
Mountain View	29
Las Vegas	26
Nuremberg	26
Munich	25
Belo Horizonte	21
Tokyo	21
Shanghai	18
Dhaka	17
Warsaw	17
Guangzhou	14
Brooklyn	13
Johannesburg	13
Frankfurt am Main	12
Montreal	12
Taipei	12
Amsterdam	11
London	11
San Jose	11
Trenton	11
Boston	10
Buffalo	10
Cairo	10
Denver	9
Jülich	9
Phoenix	9
Poplar	9
Rio de Janeiro	9
San Francisco	9
Semey	9
Tong	9
Tortona	9
Atlanta	8
Bresso	8
Changsha	8
Genoa	8
Manchester	8
Mexico City	8
Mol	8
Orem	8
Shenzhen	8
Stockholm	8
Turku	8
Chennai	7
Chicago	7
Collecchio	7
Dong Ket	7
Guarulhos	7
Hsinchu	7
Inden	7
Lyon	7
Ottawa	7
Piteå	7
Rockville	7
Tashkent	7
Cham	6
Dublin	6
Heusden-Zolder	6
Ho Chi Minh City	6
Langnau	6
Paris	6
Pisa	6
Porto Alegre	6
Saint-Sulpice	6
Totale	8.109

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Nome	#
Deliverable D4.2 START core conceptual design	579
The current ALFRED core design	368
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	326
ELSY core design static, dynamic and safety parameters with the open square FA	310
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	257
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	248
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment	238
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	236
An epithermal facility for treating brain gliomas at the TAPIRO reactor	235
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters	233
ELSY Open Square Fuel Assembly Design and Drawings	231
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	228
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length	224
EFIT -MgO/Pb Core Neutronic Preliminary Analysis	223
UOX-Fueled CLFR: core design	222
Deliverable D4.1 – START potential for fuel cycle services and options for START start-up core	208
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core	207
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC	206
Analysis of MYRRHA/FASTEF to operate in a critical mode	205
Design of an epithermal column for BNCT based on D-D fusion neutron facility	202
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment	200
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	198
Critical core solutions for FASTEF (with hollow and solid pellets)	197
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT	196
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	193
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	193
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project)	191
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	190
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	186
Parametric MCNP analyses to address the design of a neutron collimator for high-flux compact DD sources to be used in cancer radiotherapy	185
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods	184
ELSY Neutronic Analysis: Status of the Open Square Design	183
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	182
CDT/FASTEF Task 1.2 state of the art at the end of WP1	181
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	180
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	178
PDS-XADS Fuel Cycle Analysis by means of deterministic methods	178
LFR mock-up reactivity effects	174
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	173
LFR mock-up definition	172
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core	170
XT-ADS sensitivity analysis	170
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing	170
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	168
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor	167
Specification for the EFIT Core and Fuel Element	164
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	163
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level	161
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): chosen approach and preliminary ERANOS results. Some proposals for the T2.2/D2.2 work plan	161
FASTEF design changes to operate in criticai mode	156
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor	152
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases	150
Safety studies for the MYRRHA critical core with the SIMMER-III code	149
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code)	149
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library)	147
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code	147
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core	146
Preliminary FA/core design for MYRRHA/FASTEF	146
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL	146
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code	146
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data	146
Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses	145
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code)	143
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)	142
Shielding and activation calculations around the reactor core for the MYRRHA ADS design	142
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility	142
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	141
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	140
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods	139
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	139
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.	138
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode	137
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique	137
The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code	131
The ERANOS model (based on mechanical drawings) of the current frozen MYRRHA-FASTEF critical core	130
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods	129
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code	128
Pre-fronzen FA and critical core for FASTEF	127
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations	126
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core	123
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX	123
Totale	14.876

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Categoria	#
all - tutte	60.561
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	60.561

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	415	0	0	0	0	0	10	15	58	48	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	4.331	692	1.412	1.186	538	374	129	0	0	0	0	0	0
Totale													14.876