BOTAZZOLI, PIETRO
 Distribuzione geografica
Continente #
NA - Nord America 397
EU - Europa 173
AS - Asia 75
OC - Oceania 3
AF - Africa 2
Totale 650
Nazione #
US - Stati Uniti d'America 385
AT - Austria 35
UA - Ucraina 33
FI - Finlandia 27
CN - Cina 25
DE - Germania 21
ES - Italia 16
IT - Italia 16
VN - Vietnam 14
CA - Canada 11
SG - Singapore 11
JO - Giordania 10
GB - Regno Unito 6
HK - Hong Kong 5
TW - Taiwan 5
IE - Irlanda 4
SE - Svezia 4
AU - Australia 3
BE - Belgio 3
DK - Danimarca 3
HU - Ungheria 2
JP - Giappone 2
NG - Nigeria 2
RU - Federazione Russa 2
AZ - Azerbaigian 1
GL - Groenlandia 1
IL - Israele 1
KR - Corea 1
PL - Polonia 1
Totale 650
Città #
Chandler 79
Woodbridge 45
Vienna 35
Houston 33
Ann Arbor 22
Fairfield 22
Jacksonville 22
Wilmington 20
Helsinki 17
Málaga 16
Dearborn 13
Hefei 11
Ottawa 11
Amman 10
Cambridge 10
Lawrence 10
Dong Ket 9
Singapore 9
Ashburn 7
Beijing 7
Mountain View 6
Princeton 6
Seattle 6
Washington 6
Central District 5
Minneapolis 5
San Jose 5
Taipei 5
Des Moines 4
Dublin 4
Medford 4
Redwood City 4
Brussels 3
Copenhagen 3
La Spezia 3
Nanjing 3
Atlanta 2
Budapest 2
Lagos 2
New York 2
Adelaide 1
Baku 1
Bangor 1
Berlin 1
Boardman 1
Clifton 1
Columbus 1
Dallas 1
Edinburgh 1
Falkenstein 1
Frankfurt am Main 1
Lanzhou 1
Melbourne 1
Milan 1
Nanchang 1
New Orleans 1
Norwalk 1
Nuuk 1
Perth 1
Phoenix 1
Tel Aviv 1
Warsaw 1
Yellow Springs 1
Totale 511
Nome #
Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE-Cooled Nuclear Reactors 100
Assessment of the Prediction Capability of the TRANSURANUS Fuel Performance Code on the Basis of Power Ramp Tested LWR Fuel Rods 93
A Preliminary Assessment of the T91 Behaviour for the Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE Cooled Nuclear Reactors 91
Analysing Operational Transients by means of the TRANSURANUS Code 72
Simulation of Power Ramp Tested LWR Fuel Rods by means of the TRANSURANUS Code 71
A Preliminary Approach to the Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of HLM-Cooled Nuclear Reactors 62
Extension of the TRANSURANUS Code to the Analysis of Cladding Materials for Liquid Metal Cooled Fast Reactors: a Preliminary Approach 60
Modellazione del comportamento di elio in combustibili MOX ad alto burn-up ai fini dell’estensione degli strumenti di simulazione e di supporto alla progettazione delle barrette di combustibile per i reattori di generazione evolutiva ad acqua pressurizzata 40
Applying Advanced Neutron Transport Calculation for Improving Fuel Performance Codes 39
Modelli di rilascio dei gas di fissione per combustibili MOX ad elevato burnup 31
Totale 659
Categoria #
all - tutte 1.867
article - articoli 319
book - libri 0
conference - conferenze 1.127
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 3.313


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202075 0 0 0 3 13 10 9 3 9 8 16 4
2020/202175 10 0 7 0 9 9 7 12 0 5 0 16
2021/202280 2 14 6 2 13 5 1 4 4 7 6 16
2022/2023181 12 21 3 27 13 23 1 13 22 21 17 8
2023/202441 3 6 4 5 4 2 2 1 0 5 0 9
2024/20258 1 5 2 0 0 0 0 0 0 0 0 0
Totale 659