statistiche ricercatore

SAROTTO, MASSIMO

Distribuzione geografica

Continente	#
EU - Europa	6.843
NA - Nord America	6.482
AS - Asia	3.375
SA - Sud America	530
AF - Africa	132
Continente sconosciuto - Info sul continente non disponibili	86
OC - Oceania	11
Totale	17.459

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Nazione	#
US - Stati Uniti d'America	6.147
RU - Federazione Russa	3.921
SG - Singapore	1.573
IT - Italia	1.016
CN - Cina	959
GB - Regno Unito	453
BR - Brasile	451
SE - Svezia	397
DE - Germania	377
CA - Canada	282
FR - Francia	231
HK - Hong Kong	196
VN - Vietnam	145
JP - Giappone	113
AT - Austria	111
KR - Corea	88
IN - India	77
BE - Belgio	67
MA - Marocco	66
BD - Bangladesh	54
FI - Finlandia	51
NL - Olanda	42
ES - Italia	40
CH - Svizzera	38
MX - Messico	30
PL - Polonia	30
TW - Taiwan	30
AR - Argentina	27
ZA - Sudafrica	22
TR - Turchia	20
UA - Ucraina	15
UZ - Uzbekistan	15
CO - Colombia	13
IE - Irlanda	13
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
CL - Cile	6
JM - Giamaica	6
PH - Filippine	6
DK - Danimarca	5
ID - Indonesia	5
KG - Kirghizistan	5
LB - Libano	5
AL - Albania	4
AO - Angola	4
HN - Honduras	4
NP - Nepal	4
RO - Romania	4
AZ - Azerbaigian	3
BO - Bolivia	3
CZ - Repubblica Ceca	3
DO - Repubblica Dominicana	3
KE - Kenya	3
LU - Lussemburgo	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
BY - Bielorussia	2
CR - Costa Rica	2
OM - Oman	2
PR - Porto Rico	2
RS - Serbia	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
Totale	17.374

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Città	#
Dallas	1.704
Moscow	916
Chandler	853
Singapore	760
San Jose	699
Ashburn	435
Santa Clara	269
Hefei	253
Toronto	229
San Mateo	222
Southend	208
Boardman	180
Beijing	174
Council Bluffs	174
Hong Kong	171
Rome	169
New York	135
The Dalles	108
Turin	108
Hamburg	99
Salerno	94
Seoul	82
Berlin	81
Vienna	74
Lauterbourg	72
Los Angeles	71
Milan	69
Bologna	60
Columbus	60
Casablanca	59
Brussels	50
Ho Chi Minh City	49
Falkenstein	46
Helsinki	42
Miami	39
Redwood City	37
São Paulo	37
Washington	37
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	20
Frankfurt am Main	20
Shanghai	19
Dhaka	18
Johannesburg	18
Paris	17
Phoenix	17
Atlanta	15
Manchester	15
Chennai	14
Guangzhou	14
London	14
Amsterdam	12
Denver	12
Poplar	12
Taipei	12
Tashkent	12
Trenton	12
Chicago	11
Dresden	11
San Francisco	11
Boston	10
Cairo	10
Genoa	9
Hillsboro	9
Jülich	9
Madrid	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
Pisa	8
Shenzhen	8
Turku	8
Brasília	7
Collecchio	7
Dong Ket	7
Guarulhos	7
Hsinchu	7
Inden	7
Lyon	7
Totale	9.801

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Nome	#
Deliverable D4.2 START core conceptual design	617
The current ALFRED core design	455
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	369
ELSY core design static, dynamic and safety parameters with the open square FA	355
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	345
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	295
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	283
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment	270
ELSY Open Square Fuel Assembly Design and Drawings	270
An epithermal facility for treating brain gliomas at the TAPIRO reactor	266
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	261
UOX-Fueled CLFR: core design	259
EFIT -MgO/Pb Core Neutronic Preliminary Analysis	258
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length	255
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters	255
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	244
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core	241
Analysis of MYRRHA/FASTEF to operate in a critical mode	236
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT	235
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC	235
Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses	232
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment	231
Deliverable D4.1 – START potential for fuel cycle services and options for START start-up core	229
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	228
Design of an epithermal column for BNCT based on D-D fusion neutron facility	226
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project)	226
Critical core solutions for FASTEF (with hollow and solid pellets)	225
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	223
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	223
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	221
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	216
CDT/FASTEF Task 1.2 state of the art at the end of WP1	213
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	212
ELSY Neutronic Analysis: Status of the Open Square Design	212
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	211
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods	210
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	209
Parametric MCNP analyses to address the design of a neutron collimator for high-flux compact DD sources to be used in cancer radiotherapy	209
LFR mock-up reactivity effects	206
PDS-XADS Fuel Cycle Analysis by means of deterministic methods	203
LFR mock-up definition	199
Specification for the EFIT Core and Fuel Element	196
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	195
XT-ADS sensitivity analysis	193
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core	192
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	191
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing	189
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level	188
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor	188
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code	186
Safety studies for the MYRRHA critical core with the SIMMER-III code	184
FASTEF design changes to operate in criticai mode	184
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)	183
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases	183
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	182
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): chosen approach and preliminary ERANOS results. Some proposals for the T2.2/D2.2 work plan	180
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL	179
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor	175
Shielding and activation calculations around the reactor core for the MYRRHA ADS design	175
Preliminary FA/core design for MYRRHA/FASTEF	173
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library)	173
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code	173
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code)	172
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core	168
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data	166
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code)	165
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX	164
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	164
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	163
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility	162
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods	162
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.	160
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code	160
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode	157
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods	157
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique	156
The ERANOS model (based on mechanical drawings) of the current frozen MYRRHA-FASTEF critical core	152
Pre-fronzen FA and critical core for FASTEF	152
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations	150
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core	150
The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code	149
Totale	17.459

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Categoria	#
all - tutte	68.601
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	68.601

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	945	0	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	6.628	692	1.412	1.186	538	374	507	784	401	178	270	179	107
2026/2027	286	131	155	0	0	0	0	0	0	0	0	0	0
Totale													17.459