ENEA-IRIS Open Archive è l’archivio della produzione scientifica dell'ENEA, realizzato con l'obiettivo di raccogliere, catalogare e rendere facilmente accessibili in rete i risultati della ricerca. Gli autori dell’ENEA provvedono a depositare le proprie pubblicazioni (articoli su rivista, presentazioni a congressi, report, ecc.). In particolare, quelle finanziate dalla Commissione Europea nell’ambito del programma H2020 (che prevede il deposito obbligatorio in un Repository), una volta caricate, vengono automaticamente importate dal portale europeo OpenAIRE. È possibile inserire, o importare direttamente dalle banche dati previste, le informazioni descrittive del documento e anche allegare, ove consentito dalla normativa sul diritto d'autore, il testo completo della pubblicazione.

ENEA-IRIS Open Archive utilizza la piattaforma IRIS (Institutional Research Information System) sviluppata da CINECA.

SAROTTO, MASSIMO
 Distribuzione geografica
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Continente #
NA - Nord America 2.762
EU - Europa 2.337
AS - Asia 1.006
SA - Sud America 347
AF - Africa 40
Continente sconosciuto - Info sul continente non disponibili 12
OC - Oceania 10
Totale 6.514
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Nazione #
US - Stati Uniti d'America 2.514
IT - Italia 645
GB - Regno Unito 395
SG - Singapore 356
SE - Svezia 353
CN - Cina 343
BR - Brasile 314
DE - Germania 311
CA - Canada 233
RU - Federazione Russa 215
HK - Hong Kong 133
AT - Austria 107
FR - Francia 79
BE - Belgio 66
FI - Finlandia 42
IN - India 35
CH - Svizzera 30
NL - Olanda 27
TW - Taiwan 24
JP - Giappone 20
BD - Bangladesh 18
ES - Italia 17
AR - Argentina 13
TR - Turchia 12
UA - Ucraina 12
KZ - Kazakistan 11
EU - Europa 10
MX - Messico 10
EG - Egitto 9
IE - Irlanda 9
TN - Tunisia 9
UZ - Uzbekistan 8
AU - Australia 7
IR - Iran 7
VN - Vietnam 7
EC - Ecuador 6
KR - Corea 6
MA - Marocco 6
DK - Danimarca 5
DZ - Algeria 5
ZA - Sudafrica 5
CO - Colombia 4
PK - Pakistan 4
PL - Polonia 4
IQ - Iraq 3
KG - Kirghizistan 3
LB - Libano 3
LT - Lituania 3
LU - Lussemburgo 3
MY - Malesia 3
NZ - Nuova Zelanda 3
RO - Romania 3
A1 - Anonimo 2
AO - Angola 2
BG - Bulgaria 2
BO - Bolivia 2
HN - Honduras 2
JM - Giamaica 2
OM - Oman 2
PE - Perù 2
SY - Repubblica araba siriana 2
UY - Uruguay 2
VE - Venezuela 2
AE - Emirati Arabi Uniti 1
AM - Armenia 1
AZ - Azerbaigian 1
BA - Bosnia-Erzegovina 1
BY - Bielorussia 1
CI - Costa d'Avorio 1
CL - Cile 1
CZ - Repubblica Ceca 1
GA - Gabon 1
GT - Guatemala 1
GY - Guiana 1
HU - Ungheria 1
IL - Israele 1
JO - Giordania 1
KE - Kenya 1
KH - Cambogia 1
LV - Lettonia 1
MD - Moldavia 1
RS - Serbia 1
SI - Slovenia 1
SK - Slovacchia (Repubblica Slovacca) 1
SN - Senegal 1
Totale 6.514
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Città #
Chandler 853
Santa Clara 237
San Mateo 222
Toronto 219
Southend 208
Boardman 180
Singapore 142
Hong Kong 124
Ashburn 103
Hamburg 99
Salerno 94
New York 91
Berlin 81
Vienna 72
The Dalles 70
Beijing 54
Rome 53
Milan 52
Brussels 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
Nuremberg 26
Bologna 25
Los Angeles 22
Belo Horizonte 19
Shanghai 16
São Paulo 14
Dhaka 13
Guangzhou 11
Taipei 11
Trenton 11
Buffalo 10
San Jose 10
Tokyo 10
Semey 9
Tong 9
Tortona 9
Bresso 8
Cairo 8
Hefei 8
Mol 8
Amsterdam 7
Dong Ket 7
Frankfurt am Main 7
Hsinchu 7
Inden 7
Moscow 7
Ottawa 7
Piteå 7
Rio de Janeiro 7
Rockville 7
Shenzhen 7
Tashkent 7
Cham 6
Guarulhos 6
Heusden-Zolder 6
Langnau 6
London 6
Lyon 6
Pisa 6
Saint-Sulpice 6
Xian 6
Bangalore 5
Changsha 5
Dublin 5
Hanover 5
Istanbul 5
Porto Alegre 5
Wurenlingen 5
Brasília 4
Cava de' Tirreni 4
Florence 4
Genoa 4
Johannesburg 4
Madrid 4
Manaus 4
Naples 4
Osasco 4
Salvador 4
Shinonome 4
Tunis 4
Villeneuve 4
Belford Roxo 3
Bishkek 3
Bonate Sopra 3
Borås 3
Campo Grande 3
Castenaso 3
Caxias do Sul 3
Curitiba 3
Derby 3
Totale 3.888
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Nome #
The current ALFRED core design 239
Core design for the UN-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR) 182
ELSY core design static, dynamic and safety parameters with the open square FA 176
MCNP analyses of the 100 kV D-ion-based compact neutron source: irradiation performances for nIORT® treatments with different irradiation window diameters 149
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 126
UOX-Fueled CLFR: core design 119
Core design for the UOX-fueled version of the Westinghouse Commercial Lead Fast Reactor (CLFR) 115
ELSY Open Square Fuel Assembly Design and Drawings 113
Core design for the UOX-fueled version of the Westinghouse Prototype Lead Fast Reactor (PLFR) 112
The physical principles of the ERANOS neutronic deterministic code and its application to the LFR and VENUS-F critical cores 105
ELSY Neutronic Analysis: Status of the Open Square Design 101
Parametric MCNP analyses to address the design of a neutron collimator for high-flux compact DD sources to be used in cancer radiotherapy 100
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project) 98
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 96
Comparison between Cross-section data for deterministic and Monte Carlo calculations in the TRADE experiment 95
Neutronic analyses of the FREYA experiments in support of the Alfred lead-cooled fast reactor core design and licensing 95
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 95
Analysis of MYRRHA/FASTEF to operate in a critical mode 94
Critical core design of MYRRHA-FASTEF: refinement of shutdown systems and neutronic characterisation of the equilibrium sub-cycle core 93
Evaluation of the PDS-XADS reactivity level at Beginning of Cycle by means of deterministic methods 92
Design of an epithermal column for BNCT based on D-D fusion neutron facility 91
Evaluation of Multi-Temperature Cross-sections for deterministic calculations in the TRADE experiment 91
EFIT -MgO/Pb Core Neutronic Preliminary Analysis 91
An epithermal facility for treating brain gliomas at the TAPIRO reactor 90
PDS-XADS Fuel Cycle Analysis by means of deterministic methods 90
Procedure for pin-by-pin reconstruction of an ERANOS flux (power) in a Fuel Assembly 90
A possible solution for the MYRRHA-FASTEF critical core with the 30 wt. % Pu mass content: the increasing of fissile length 89
Preliminary Neutronic Analysis of the three Zones EFIT-MgO/Pb Core 87
FASTEF design changes to operate in criticai mode 84
Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor 82
Critical core design of MYRRHA-FASTEF: main reactivitycoefficients at BoL, BoC and EoC 82
Results of the validation campaign of neutronic codes and recommendations for the correct application to LFR systems 82
Deliverable D4.1 – START potential for fuel cycle services and options for START start-up core 80
Specification for the EFIT Core and Fuel Element 78
XT-ADS sensitivity analysis 78
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions 77
The impact of different cell calculation methodologies on the calculated ADS-DF reactivity level 77
Critical core solutions for FASTEF (with hollow and solid pellets) 75
LFR mock-up reactivity effects 75
Deliverable D4.2 START core conceptual design 74
LFR mock-up definition 74
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): chosen approach and preliminary ERANOS results. Some proposals for the T2.2/D2.2 work plan 73
Preliminary neutronic analyses of the MYRTHE-CC11 core results with the ERANOS code 73
Information to support the LFR ALFRED FA/core definition on VENUS: preliminary spectra analyses (with the ERANOS deterministic code) 72
CDT/FASTEF Task 1.2 state of the art at the end of WP1 71
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design 71
Preliminary neutronic analysis of minimum critical and sub-critical cores (ERANOS deterministic code) 71
The VENUS-F CC6 core: ERANOS neutronic analyses and comparison with experimental data 71
Preliminary FA/core design for MYRRHA/FASTEF 70
A Parabolic Collimator as a Possible Solution in the TAPIRO Epithermal Column used for Patient Treatment with BNCT 70
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 70
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases 69
Safety studies for the MYRRHA critical core with the SIMMER-III code 68
Neutronic analysis of maximum cores with the ERANOS deterministic code (and JEFF3.1 nuclear data library) 68
Possible working range of the MYRRHA core and basic neutronic parameters for safety analyses 68
Spectrum Indexes and Minor Actinide Fission Rate measurements in several fast lead critical cores in the Zero Power VENUS-F Reactor 68
Shielding and activation calculations for the FASTEF-MYRRHA ADS design in the subcritical operation mode 67
Neutronic analysis of minimum cores and first investigation on maximum cores with the ERANOS deterministic code 67
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 66
Shielding and activation calculations around the reactor core for the MYRRHA ADS design 65
Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor 64
MYRRHA-FASTEF sub-critical core (30 wt. % Epu): Temperature feedback effects, main reactivity (and power) coefficients at BoL 64
An outcome of the EU FP7 CP CDT: the MYRRHA-FASTEF FA/core design 63
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 60
Preliminary neutronic analyses of the CC10 core experimental results with the ERANOS code 60
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements 60
Preliminary neutronic and thermal-hydraulic analyses of a fast (LBE cooled) experimental reactor / irradiation facility 59
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. 59
Possible Solutions for the Neutronic Design of the two zones EFIT-MgO/Pb Core 58
Results of the validation campaign of neutronic codes and reccomandations for the correct application to LFR systems 58
The ERANOS model (based on mechanical drawings) of the current frozen MYRRHA-FASTEF critical core 57
The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project) 56
Geometrical Design of the Neutron Reflector - Collimator used in the TAPIRO Facility to treat Brain Gliomas by the BNCT Technique 56
First approach/proposal for the MYRRHA-FASTEF sub-critical core by the 30 wt.% Pu mass content in MOX 54
Pre-fronzen FA and critical core for FASTEF 52
Preliminary Evaluation of the ETD I EFIT Neutronic Performances with Deterministic Methods 48
IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods 48
Proposed methodology for shielding/activation evaluations in criticai and sub-critical MYRRHA-FASTEF equilibrium configurations 47
Scoping neutronic investigations for MYRRHA critical (and sub-critical) core 45
The MYRRHA-FASTEF critical core: neutronic estimations at BoL with the ERANOS deterministic code 43
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS 25
Totale 6.586
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Categoria #
all - tutte 39.781
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 39.781
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20205 0 0 0 0 0 0 0 0 0 0 2 3
2020/2021652 27 27 15 17 151 10 15 58 48 38 220 26
2021/2022957 12 242 12 55 119 29 40 192 83 15 71 87
2022/20231.828 125 353 183 206 83 272 22 125 224 52 135 48
2023/2024921 69 42 123 36 108 146 25 82 63 49 60 118
2024/20252.126 24 254 70 99 353 148 215 269 365 200 129 0
Totale 6.586