statistiche ricercatore

SAROTTO, MASSIMO

Distribuzione geografica

Continente	#
EU - Europa	6.738
NA - Nord America	6.290
AS - Asia	3.369
SA - Sud America	525
AF - Africa	132
Continente sconosciuto - Info sul continente non disponibili	13
OC - Oceania	11
Totale	17.078

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Nazione	#
US - Stati Uniti d'America	5.962
RU - Federazione Russa	3.921
SG - Singapore	1.573
CN - Cina	958
IT - Italia	946
GB - Regno Unito	452
BR - Brasile	449
SE - Svezia	386
DE - Germania	373
CA - Canada	280
FR - Francia	221
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
BD - Bangladesh	53
FI - Finlandia	51
NL - Olanda	42
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
CR - Costa Rica	2
OM - Oman	2
SY - Repubblica araba siriana	2
TH - Thailandia	2
BA - Bosnia-Erzegovina	1
BB - Barbados	1
BH - Bahrain	1
BJ - Benin	1
BT - Bhutan	1
CI - Costa d'Avorio	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
Totale	17.068

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Città	#
Dallas	1.701
Moscow	916
Chandler	853
Singapore	760
San Jose	695
Ashburn	425
Santa Clara	268
Hefei	253
Toronto	229
San Mateo	222
Southend	208
Boardman	180
Beijing	174
Hong Kong	171
Rome	161
New York	134
The Dalles	108
Hamburg	99
Salerno	94
Council Bluffs	93
Seoul	82
Berlin	81
Turin	79
Vienna	74
Lauterbourg	72
Los Angeles	70
Milan	68
Columbus	60
Bologna	59
Casablanca	59
Brussels	50
Ho Chi Minh City	49
Falkenstein	46
Helsinki	42
Miami	39
Redwood City	37
São Paulo	37
Washington	36
Marseille	34
Orem	34
Ann Arbor	29
Mountain View	29
Nuremberg	27
Hanoi	26
Las Vegas	26
Munich	25
Buffalo	23
Tokyo	22
Warsaw	22
Belo Horizonte	21
Montreal	21
Brooklyn	19
Shanghai	19
Dhaka	18
Johannesburg	18
Frankfurt am Main	16
Manchester	15
Chennai	14
Guangzhou	14
London	14
Amsterdam	12
Denver	12
Phoenix	12
Taipei	12
Tashkent	12
Atlanta	11
Chicago	11
Dresden	11
Paris	11
Poplar	11
Trenton	11
Boston	10
Cairo	10
San Francisco	10
Genoa	9
Hillsboro	9
Jülich	9
Mexico City	9
Rio de Janeiro	9
Semey	9
Stockholm	9
Tong	9
Tortona	9
Bresso	8
Changsha	8
Da Nang	8
Dublin	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	9.634

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Nome	#
Deliverable D4.2 START core conceptual design	615
The current ALFRED core design	439
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	364
ELSY core design static, dynamic and safety parameters with the open square FA	346
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	302
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	293
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	279
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment	268
ELSY Open Square Fuel Assembly Design and Drawings	265
An epithermal facility for treating brain gliomas at the TAPIRO reactor	264
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	260
UOX-Fueled CLFR: core design	258
EFIT -MgO/Pb Core Neutronic Preliminary Analysis	256
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length	253
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters	251
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core	237
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT	234
Analysis of MYRRHA/FASTEF to operate in a critical mode	234
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC	232
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment	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	228
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	226
Design of an epithermal column for BNCT based on D-D fusion neutron facility	224
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project)	223
Critical core solutions for FASTEF (with hollow and solid pellets)	222
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	220
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	218
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	217
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	212
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	211
CDT/FASTEF Task 1.2 state of the art at the end of WP1	211
ELSY Neutronic Analysis: Status of the Open Square Design	210
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	210
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods	208
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	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
PDS-XADS Fuel Cycle Analysis by means of deterministic methods	200
LFR mock-up reactivity effects	200
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	198
LFR mock-up definition	197
Specification for the EFIT Core and Fuel Element	194
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	194
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core	191
XT-ADS sensitivity analysis	191
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	188
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing	188
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level	186
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor	186
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code	183
FASTEF design changes to operate in criticai mode	182
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases	179
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
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	179
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)	176
Safety studies for the MYRRHA critical core with the SIMMER-III code	175
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL	175
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor	173
Shielding and activation calculations around the reactor core for the MYRRHA ADS design	173
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code	172
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library)	171
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code)	171
Preliminary FA/core design for MYRRHA/FASTEF	169
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core	165
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data	165
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code)	164
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX	163
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility	161
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
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	161
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods	160
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
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code	159
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode	155
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique	154
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods	153
Pre-fronzen FA and critical core for FASTEF	150
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations	148
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core	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	147
Totale	17.151

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Categoria	#
all - tutte	66.609
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	66.609

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	26	0	0	0	0	0	0	0	0	0	0	0	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	6.606	692	1.412	1.186	538	374	507	784	401	178	270	179	85
Totale													17.151