statistiche ricercatore

SAROTTO, MASSIMO

Distribuzione geografica

Continente	#
NA - Nord America	2.686
EU - Europa	2.114
AS - Asia	834
SA - Sud America	237
AF - Africa	22
Continente sconosciuto - Info sul continente non disponibili	12
OC - Oceania	10
Totale	5.915

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Nazione	#
US - Stati Uniti d'America	2.443
IT - Italia	627
GB - Regno Unito	395
SE - Svezia	353
CN - Cina	343
DE - Germania	270
SG - Singapore	241
CA - Canada	232
BR - Brasile	215
AT - Austria	96
HK - Hong Kong	90
RU - Federazione Russa	81
FR - Francia	72
BE - Belgio	65
FI - Finlandia	42
IN - India	35
CH - Svizzera	30
NL - Olanda	23
JP - Giappone	19
TW - Taiwan	19
BD - Bangladesh	18
ES - Italia	17
KZ - Kazakistan	11
UA - Ucraina	11
EU - Europa	10
TR - Turchia	10
AR - Argentina	9
IE - Irlanda	8
MX - Messico	8
TN - Tunisia	8
UZ - Uzbekistan	8
AU - Australia	7
IR - Iran	7
VN - Vietnam	7
KR - Corea	6
DK - Danimarca	5
DZ - Algeria	3
EC - Ecuador	3
IQ - Iraq	3
LT - Lituania	3
LU - Lussemburgo	3
MY - Malesia	3
NZ - Nuova Zelanda	3
PK - Pakistan	3
RO - Romania	3
A1 - Anonimo	2
AO - Angola	2
BG - Bulgaria	2
BO - Bolivia	2
CO - Colombia	2
EG - Egitto	2
KG - Kirghizistan	2
LB - Libano	2
MA - Marocco	2
PE - Perù	2
PL - Polonia	2
SY - Repubblica araba siriana	2
AE - Emirati Arabi Uniti	1
AZ - Azerbaigian	1
CI - Costa d'Avorio	1
CL - Cile	1
CZ - Repubblica Ceca	1
GA - Gabon	1
GT - Guatemala	1
GY - Guiana	1
HN - Honduras	1
HU - Ungheria	1
IL - Israele	1
JM - Giamaica	1
KE - Kenya	1
KH - Cambogia	1
LV - Lettonia	1
MD - Moldavia	1
OM - Oman	1
SI - Slovenia	1
SK - Slovacchia (Repubblica Slovacca)	1
SN - Senegal	1
UY - Uruguay	1
VE - Venezuela	1
ZA - Sudafrica	1
Totale	5.915

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Città	#
Chandler	853
Santa Clara	237
San Mateo	222
Toronto	219
Southend	208
Boardman	180
Singapore	132
Ashburn	102
Salerno	94
New York	91
Berlin	81
Hong Kong	81
Hamburg	72
Vienna	69
Beijing	54
Rome	53
Brussels	49
Milan	49
Falkenstein	46
Helsinki	41
Turin	39
Redwood City	37
Washington	35
Miami	34
Marseille	33
Ann Arbor	29
Mountain View	29
Council Bluffs	27
Las Vegas	26
Bologna	23
Los Angeles	22
Belo Horizonte	17
Nuremberg	16
Shanghai	16
Dhaka	13
Guangzhou	11
Taipei	11
Trenton	11
Buffalo	10
San Jose	10
São Paulo	10
Semey	9
Tokyo	9
Tong	9
Tortona	9
Bresso	8
Hefei	8
Amsterdam	7
Dong Ket	7
Inden	7
Mol	7
Ottawa	7
Piteå	7
Rockville	7
Shenzhen	7
Tashkent	7
Cham	6
Heusden-Zolder	6
Langnau	6
London	6
Lyon	6
Moscow	6
Pisa	6
Saint-Sulpice	6
Xian	6
Bangalore	5
Changsha	5
Hanover	5
Istanbul	5
Rio de Janeiro	5
Wurenlingen	5
Cava de' Tirreni	4
Dublin	4
Florence	4
Genoa	4
Madrid	4
Naples	4
Porto Alegre	4
Shinonome	4
Villeneuve	4
Bonate Sopra	3
Borås	3
Castenaso	3
Curitiba	3
Derby	3
Faenza	3
Ferrara	3
Frankfurt am Main	3
Fremont	3
Garbsen	3
Harbin	3
Hsinchu	3
Kowloon	3
Lomas de Zamora	3
Manaus	3
North Charleston	3
Osasco	3
Sydney	3
Taichung	3
Taubaté	3
Totale	3.687

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Nome	#
The current ALFRED core design	214
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	175
ELSY core design static, dynamic and safety parameters with the open square FA	164
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters	140
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	121
UOX-Fueled CLFR: core design	112
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	108
ELSY Open Square Fuel Assembly Design and Drawings	104
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	104
ELSY Neutronic Analysis: Status of the Open Square Design	97
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	96
Parametric MCNP analyses to address the design of a neutron collimator for high-flux compact DD sources to be used in cancer radiotherapy	94
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project)	89
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment	89
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	88
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing	88
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	88
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment	87
PDS-XADS Fuel Cycle Analysis by means of deterministic methods	87
Analysis of MYRRHA/FASTEF to operate in a critical mode	87
Design of an epithermal column for BNCT based on D-D fusion neutron facility	83
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length	83
EFIT -MgO/Pb Core Neutronic Preliminary Analysis	81
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	81
An epithermal facility for treating brain gliomas at the TAPIRO reactor	80
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core	79
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core	79
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods	78
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	77
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	75
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	75
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC	75
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level	74
Specification for the EFIT Core and Fuel Element	73
XT-ADS sensitivity analysis	72
FASTEF design changes to operate in criticai mode	72
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): chosen approach and preliminary ERANOS results. Some proposals for the T2.2/D2.2 work plan	68
LFR mock-up definition	68
LFR mock-up reactivity effects	68
Critical core solutions for FASTEF (with hollow and solid pellets)	67
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code	67
Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses	66
Deliverable D4.1 – START potential for fuel cycle services and options for START start-up core	64
CDT/FASTEF Task 1.2 state of the art at the end of WP1	64
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library)	64
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data	64
Safety studies for the MYRRHA critical core with the SIMMER-III code	63
Preliminary FA/core design for MYRRHA/FASTEF	63
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT	63
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	63
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	62
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code)	62
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor	61
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor	61
Deliverable D4.2 START core conceptual design	60
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code)	60
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code	58
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	57
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode	56
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code	56
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL	55
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	55
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.	54
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	54
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)	53
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases	53
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core	53
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	53
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	53
The ERANOS model (based on mechanical drawings) of the current frozen MYRRHA-FASTEF critical core	52
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX	52
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique	51
Shielding and activation calculations around the reactor core for the MYRRHA ADS design	50
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility	50
Pre-fronzen FA and critical core for FASTEF	48
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods	43
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core	43
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods	43
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations	42
The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code	40
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	16
Totale	5.987

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Categoria	#
all - tutte	37.263
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	37.263

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	27	0	0	0	0	0	0	0	0	6	16	2	3
2020/2021	652	27	27	15	17	151	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	1.527	24	254	70	99	353	148	215	269	95	0	0	0
Totale													5.987