MOUSAVIBALGEHSHIRI, SEYED KAMAL
 Distribuzione geografica
Continente #
EU - Europa 154
NA - Nord America 83
AS - Asia 72
Continente sconosciuto - Info sul continente non disponibili 13
SA - Sud America 4
AF - Africa 3
Totale 329
Nazione #
IT - Italia 131
US - Stati Uniti d'America 80
BD - Bangladesh 15
CN - Cina 15
SG - Singapore 15
VN - Vietnam 13
NL - Olanda 7
FR - Francia 4
GB - Regno Unito 4
HK - Hong Kong 4
ID - Indonesia 3
SE - Svezia 3
BR - Brasile 2
DE - Germania 2
IN - India 2
JM - Giamaica 2
NO - Norvegia 2
AO - Angola 1
AR - Argentina 1
CA - Canada 1
CO - Colombia 1
GE - Georgia 1
HR - Croazia 1
KE - Kenya 1
PH - Filippine 1
PK - Pakistan 1
TW - Taiwan 1
UZ - Uzbekistan 1
ZA - Sudafrica 1
Totale 316
Città #
Genoa 90
San Jose 14
Ashburn 12
St Louis 10
Ho Chi Minh City 7
Milan 6
Singapore 5
Hong Kong 4
Beijing 3
Livorno 3
Stockholm 3
Amsterdam 2
Boardman 2
Catania 2
Frankfurt am Main 2
Houston 2
Kingston 2
Los Angeles 2
New York 2
Omaha 2
Rome 2
Thousand Oaks 2
Antipolo City 1
Banqiao 1
Batumi 1
Bolzano 1
Buffalo 1
Burley 1
Bắc Ninh 1
Canary Wharf 1
Castanhal 1
Chiavari 1
Chicago 1
Cibitung 1
City of London 1
Council Bluffs 1
Dallas 1
Dhaka 1
El Dorado Hills 1
Gresik 1
Hanoi 1
Hortolândia 1
Jizzakh 1
Jodhpur 1
Johannesburg 1
Laurel 1
Lauterbourg 1
Long Beach 1
Luanda 1
Lucca 1
Montreal 1
Naples 1
North Charleston 1
North Las Vegas 1
Norwalk 1
Perugia 1
Petilia Policastro 1
Pontianak 1
Popayán 1
Preganziol 1
Quận Mười 1
Ramos Mejía 1
Richmond 1
Salt Lake City 1
Santa Clara 1
Shanghai 1
Springfield 1
Tianjin 1
Topeka 1
Tucson 1
Tân Bình 1
Upminster 1
Venice 1
Waterbury 1
Zagreb 1
Zhengzhou 1
Zhuhai 1
Totale 234
Nome #
A review of strategies and challenges of super critical water-cooled reactor (SCWR) deployment and technology readiness assessment of a SCWR- SMR design 133
Nuclear Reactor Physics and Operation: Neutronic Analysis for Nuclear Reactor Design 86
Plentiful Tritium generation by a FFHR to feed a fusion power plant with simplified blanket 82
Preliminary Thermal-hydraulic Analysis of Proposed Simplified Test Blanket Module (TBM) as a Subcritical Reactor Driven by Fusion Neutrons 16
Corrigendum to “ Plentiful Tritium generation by a FFHR to feed a fusion power plant with simplified blanket” [Fusion Engineering and Design 217 (2025) 115138] 8
Preliminary Thermal-hydraulic Analysis of Subcritical Fission Zone for Conceptual Test Blanket Module Driven by Fusion Neutrons 4
Totale 329
Categoria #
all - tutte 730
article - articoli 246
book - libri 162
conference - conferenze 322
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 1.460


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2024/202533 0 0 0 0 0 0 0 12 2 4 5 10
2025/2026224 10 12 19 21 24 17 27 23 10 25 10 26
2026/202772 23 34 15 0 0 0 0 0 0 0 0 0
Totale 329