statistiche ricercatore

SAROTTO, MASSIMO

Distribuzione geografica

Continente	#
NA - Nord America	2.220
EU - Europa	1.658
AS - Asia	325
SA - Sud America	21
Continente sconosciuto - Info sul continente non disponibili	12
OC - Oceania	9
AF - Africa	5
Totale	4.250

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Nazione	#
US - Stati Uniti d'America	1.989
IT - Italia	462
GB - Regno Unito	384
SE - Svezia	352
CA - Canada	229
CN - Cina	177
DE - Germania	132
AT - Austria	89
FR - Francia	64
BE - Belgio	55
HK - Hong Kong	43
FI - Finlandia	42
IN - India	30
CH - Svizzera	22
TW - Taiwan	19
BR - Brasile	17
JP - Giappone	16
ES - Italia	13
EU - Europa	10
KZ - Kazakistan	10
SG - Singapore	10
NL - Olanda	8
UA - Ucraina	8
AU - Australia	7
IR - Iran	7
VN - Vietnam	7
IE - Irlanda	6
DK - Danimarca	4
RU - Federazione Russa	4
AR - Argentina	3
LU - Lussemburgo	3
A1 - Anonimo	2
BG - Bulgaria	2
DZ - Algeria	2
KR - Corea	2
MA - Marocco	2
MX - Messico	2
NZ - Nuova Zelanda	2
PL - Polonia	2
RO - Romania	2
AE - Emirati Arabi Uniti	1
CO - Colombia	1
CZ - Repubblica Ceca	1
EG - Egitto	1
HU - Ungheria	1
IQ - Iraq	1
LV - Lettonia	1
MY - Malesia	1
SI - Slovenia	1
TR - Turchia	1
Totale	4.250

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Città	#
Chandler	853
San Mateo	222
Toronto	217
Southend	208
Salerno	94
Ashburn	90
Berlin	81
Boardman	80
New York	74
Vienna	67
Beijing	50
Brussels	44
Helsinki	41
Hong Kong	37
Redwood City	37
Rome	36
Washington	35
Marseille	33
Ann Arbor	29
Mountain View	29
Las Vegas	26
Milan	23
Turin	21
Bologna	20
Los Angeles	17
Shanghai	12
Taipei	11
Trenton	11
Buffalo	10
San Jose	10
Miami	9
Semey	9
Tong	9
Tortona	9
Belo Horizonte	8
Bresso	8
Hefei	8
Dong Ket	7
Inden	7
Piteå	7
Rockville	7
Heusden-Zolder	6
Langnau	6
Ottawa	6
Saint-Sulpice	6
Tokyo	6
Xian	6
Bangalore	5
Changsha	5
Guangzhou	5
Hanover	5
Wurenlingen	5
Cava de' Tirreni	4
Florence	4
Mol	4
Shinonome	4
Villeneuve	4
Borås	3
Castenaso	3
Faenza	3
Ferrara	3
Fremont	3
Garbsen	3
Hsinchu	3
Kowloon	3
London	3
North Charleston	3
Sydney	3
Taichung	3
Abbiategrasso	2
Alexandria	2
Bonn	2
Bra	2
Bracciano	2
Brighton	2
Calderino	2
Cassine	2
Central District	2
Chengdu	2
Chennai	2
Chicago	2
Dallas	2
Dronten	2
Dublin	2
Einsiedeln	2
Fairfield	2
Frankfurt am Main	2
Frascati	2
Gurgaon	2
Hangzhou	2
Leopoldshafen	2
Linfen	2
Lomas de Zamora	2
Los Altos	2
Luxembourg	2
Manerbio	2
Manosque	2
Mazzano Romano	2
Mioveni	2
Moscow	2
Totale	2.785

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Nome	#
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	131
ELSY core design static, dynamic and safety parameters with the open square FA	130
The current ALFRED core design	130
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters	123
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	97
UOX-Fueled CLFR: core design	96
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	88
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	85
ELSY Neutronic Analysis: Status of the Open Square Design	77
Parametric MCNP analyses to address the design of a neutron collimator for high-flux compact DD sources to be used in cancer radiotherapy	77
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	74
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment	71
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core	69
ELSY Open Square Fuel Assembly Design and Drawings	69
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	69
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project)	68
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	68
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing	68
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment	64
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level	61
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	60
An epithermal facility for treating brain gliomas at the TAPIRO reactor	59
Design of an epithermal column for BNCT based on D-D fusion neutron facility	59
EFIT -MgO/Pb Core Neutronic Preliminary Analysis	57
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	56
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	56
Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses	56
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	56
Specification for the EFIT Core and Fuel Element	54
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core	54
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): chosen approach and preliminary ERANOS results. Some proposals for the T2.2/D2.2 work plan	54
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length	54
Critical core solutions for FASTEF (with hollow and solid pellets)	52
Analysis of MYRRHA/FASTEF to operate in a critical mode	51
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC	51
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code)	50
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library)	49
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data	49
Safety studies for the MYRRHA critical core with the SIMMER-III code	48
PDS-XADS Fuel Cycle Analysis by means of deterministic methods	48
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor	47
LFR mock-up reactivity effects	47
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code)	46
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	45
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	45
CDT/FASTEF Task 1.2 state of the art at the end of WP1	45
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods	44
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor	43
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode	42
LFR mock-up definition	42
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	41
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code	41
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	41
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)	40
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core	40
Preliminary FA/core design for MYRRHA/FASTEF	40
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique	40
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility	40
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code	40
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	40
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases	39
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT	39
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	39
Shielding and activation calculations around the reactor core for the MYRRHA ADS design	38
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX	38
Deliverable D4.1 – START potential for fuel cycle services and options for START start-up core	37
The ERANOS model (based on mechanical drawings) of the current frozen MYRRHA-FASTEF critical core	37
Pre-fronzen FA and critical core for FASTEF	37
FASTEF design changes to operate in criticai mode	37
XT-ADS sensitivity analysis	36
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL	36
Deliverable D4.2 START core conceptual design	35
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	33
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.	32
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations	31
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods	30
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core	30
The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code	26
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods	26
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code	26
Totale	4.319

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Categoria	#
all - tutte	26.803
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	26.803

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	102	0	0	0	0	44	13	7	11	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	780	69	42	123	36	108	146	25	82	63	49	37	0
Totale													4.319