statistiche ricercatore

SAROTTO, MASSIMO

Distribuzione geografica

Continente	#
NA - Nord America	7.173
EU - Europa	6.976
AS - Asia	3.416
SA - Sud America	569
AF - Africa	133
Continente sconosciuto - Info sul continente non disponibili	86
OC - Oceania	11
Totale	18.364

Salva come PNG Salva come JPEG

Nazione	#
US - Stati Uniti d'America	6.805
RU - Federazione Russa	3.921
SG - Singapore	1.573
IT - Italia	1.131
CN - Cina	970
BR - Brasile	466
GB - Regno Unito	460
SE - Svezia	397
DE - Germania	377
CA - Canada	291
FR - Francia	232
HK - Hong Kong	197
VN - Vietnam	150
JP - Giappone	113
AT - Austria	111
KR - Corea	88
IN - India	77
BE - Belgio	67
MA - Marocco	66
BD - Bangladesh	56
FI - Finlandia	51
NL - Olanda	42
ES - Italia	40
CH - Svizzera	38
MX - Messico	37
AR - Argentina	30
PL - Polonia	30
TW - Taiwan	30
ZA - Sudafrica	22
EC - Ecuador	21
TR - Turchia	20
CO - Colombia	19
IE - Irlanda	16
MY - Malesia	16
UA - Ucraina	15
UZ - Uzbekistan	15
EG - Egitto	12
KZ - Kazakistan	12
ID - Indonesia	11
IQ - Iraq	11
TN - Tunisia	11
VE - Venezuela	11
EU - Europa	10
PH - Filippine	10
PK - Pakistan	10
SA - Arabia Saudita	10
JM - Giamaica	9
AU - Australia	8
DK - Danimarca	8
AL - Albania	7
DZ - Algeria	7
HN - Honduras	7
IR - Iran	7
LT - Lituania	7
CL - Cile	6
CR - Costa Rica	5
KG - Kirghizistan	5
LB - Libano	5
NP - Nepal	5
AO - Angola	4
RO - Romania	4
TH - Thailandia	4
UY - Uruguay	4
AE - Emirati Arabi Uniti	3
AZ - Azerbaigian	3
BO - Bolivia	3
CZ - Repubblica Ceca	3
DO - Repubblica Dominicana	3
GT - Guatemala	3
KE - Kenya	3
LU - Lussemburgo	3
NZ - Nuova Zelanda	3
PE - Perù	3
PR - Porto Rico	3
PY - Paraguay	3
TT - Trinidad e Tobago	3
A1 - Anonimo	2
AM - Armenia	2
BG - Bulgaria	2
BH - Bahrain	2
BY - Bielorussia	2
EE - Estonia	2
GP - Guadalupe	2
GY - Guiana	2
MQ - Martinica	2
OM - Oman	2
RS - Serbia	2
SY - Repubblica araba siriana	2
BA - Bosnia-Erzegovina	1
BB - Barbados	1
BJ - Benin	1
BT - Bhutan	1
CG - Congo	1
CI - Costa d'Avorio	1
GA - Gabon	1
GD - Grenada	1
GF - Guiana Francese	1
HR - Croazia	1
HU - Ungheria	1
IL - Israele	1
Totale	18.275

Salva come PNG Salva come JPEG

Città	#
Dallas	1.707
Moscow	916
Chandler	853
Singapore	760
San Jose	699
Ashburn	587
Santa Clara	275
Council Bluffs	270
Hefei	253
Toronto	231
San Mateo	222
Southend	208
Rome	187
Boardman	180
Beijing	175
Hong Kong	171
New York	137
Turin	120
The Dalles	108
Hamburg	99
Salerno	94
Phoenix	84
Seoul	82
Berlin	81
Los Angeles	78
Milan	77
Vienna	74
Lauterbourg	72
Bologna	61
Columbus	61
Casablanca	59
Brussels	50
Ho Chi Minh City	50
Falkenstein	46
Miami	43
Helsinki	42
São Paulo	41
Redwood City	37
Washington	37
Orem	35
Marseille	34
North Tonawanda	33
Manheim	30
Ann Arbor	29
Mountain View	29
Hanoi	28
Atlanta	27
Las Vegas	27
Nuremberg	27
Munich	25
Buffalo	23
Tokyo	22
Warsaw	22
Belo Horizonte	21
Brooklyn	21
Montreal	21
Frankfurt am Main	20
Shanghai	20
Dhaka	19
Johannesburg	18
Paris	17
Chicago	16
Manchester	15
Chennai	14
Guangzhou	14
London	14
Brasília	13
Denver	13
Guidonia Montecelio	13
North Bergen	13
Amsterdam	12
Poplar	12
Taipei	12
Tashkent	12
Trenton	12
Dresden	11
Genoa	11
San Francisco	11
Boston	10
Cairo	10
Hillsboro	10
Haiphong	9
Jülich	9
Madrid	9
Mexico City	9
Rio de Janeiro	9
Semey	9
Shenzhen	9
Stockholm	9
Tong	9
Tortona	9
Bresso	8
Changsha	8
Da Nang	8
Dublin	8
Mol	8
Pisa	8
Turku	8
Collecchio	7
Dong Ket	7
Totale	10.283

Salva come PNG Salva come JPEG

Nome	#
Deliverable D4.2 START core conceptual design	631
The current ALFRED core design	502
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	387
ELSY core design static, dynamic and safety parameters with the open square FA	374
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	364
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR)	308
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR)	307
ELSY Open Square Fuel Assembly Design and Drawings	293
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment	280
An epithermal facility for treating brain gliomas at the TAPIRO reactor	273
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly	270
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length	269
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT	267
UOX-Fueled CLFR: core design	266
EFIT -MgO/Pb Core Neutronic Preliminary Analysis	265
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters	265
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS	253
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core	253
Deliverable D4.1 – START potential for fuel cycle services and options for START start-up core	250
Analysis of MYRRHA/FASTEF to operate in a critical mode	246
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC	246
Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses	244
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment	241
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	239
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project)	238
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores	236
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	235
Design of an epithermal column for BNCT based on D-D fusion neutron facility	233
Critical core solutions for FASTEF (with hollow and solid pellets)	233
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	232
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor	230
CDT/FASTEF Task 1.2 state of the art at the end of WP1	227
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design	225
ELSY Neutronic Analysis: Status of the Open Square Design	219
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	218
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems	218
Parametric MCNP analyses to address the design of a neutron collimator for high-flux compact DD sources to be used in cancer radiotherapy	217
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods	215
LFR mock-up definition	214
LFR mock-up reactivity effects	213
PDS-XADS Fuel Cycle Analysis by means of deterministic methods	211
Specification for the EFIT Core and Fuel Element	205
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	204
FASTEF design changes to operate in criticai mode	201
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	200
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core	200
XT-ADS sensitivity analysis	199
Safety studies for the MYRRHA critical core with the SIMMER-III code	197
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code	196
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor	195
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases	193
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level	193
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing	193
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)	190
Shielding and activation calculations around the reactor core for the MYRRHA ADS design	190
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems	190
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL	189
Preliminary FA/core design for MYRRHA/FASTEF	187
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): chosen approach and preliminary ERANOS results. Some proposals for the T2.2/D2.2 work plan	187
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library)	186
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor	184
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code	179
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode	177
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core	177
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code)	177
The ERANOS model (based on mechanical drawings) of the current frozen MYRRHA-FASTEF critical core	176
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code)	176
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data	173
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility	171
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code	170
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	170
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX	169
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.	169
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods	168
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods	168
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	167
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique	164
The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code	159
Pre-fronzen FA and critical core for FASTEF	157
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core	157
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations	154
Totale	18.364

Salva come PNG Salva come JPEG

Categoria	#
all - tutte	71.574
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	71.574

Salva come PNG Salva come JPEG

	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2021/2022	691	0	0	0	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	1.191	131	246	403	411	0	0	0	0	0	0	0	0
Totale													18.364