BURN, KENNETH WILLIAM
 Distribuzione geografica
Continente #
EU - Europa 709
NA - Nord America 708
AS - Asia 60
Continente sconosciuto - Info sul continente non disponibili 3
Totale 1480
Nazione #
US - Stati Uniti d'America 624
IT - Italia 221
GB - Regno Unito 139
SE - Svezia 129
AT - Austria 120
CA - Canada 84
DE - Germania 39
BE - Belgio 27
VN - Vietnam 26
CN - Cina 22
FI - Finlandia 17
FR - Francia 11
IN - India 8
NL - Olanda 4
EU - Europa 3
HK - Hong Kong 2
ES - Italia 1
IR - Iran 1
MO - Macao, regione amministrativa speciale della Cina 1
UA - Ucraina 1
Totale 1480
Città #
Chandler 362
Vienna 86
San Mateo 84
Toronto 83
Southend 78
Rome 37
Berlin 32
Brussels 27
Dong Ket 26
Bologna 18
Helsinki 17
Redwood City 11
Mountain View 10
Mazzano Romano 9
Ann Arbor 8
Canale Monterano 8
Minerbio 5
Rockville 5
Turin 5
Hefei 4
Paris 4
Port Jefferson 4
Rimini 4
Borås 3
Falls Church 3
San Giuliano Terme 3
Seregno 3
Beijing 2
Bracciano 2
Changsha 2
Ciampino 2
Cremona 2
Dallas 2
Frankfurt am Main 2
Milan 2
Redmond 2
Stockholm 2
Albany 1
Alexandria 1
Amsterdam 1
Ashburn 1
Bellinzago Lombardo 1
Brooklyn 1
Cabiate 1
Cava de' Tirreni 1
Chatsworth 1
Cheyenne 1
Como 1
Edinburgh 1
Fiumicino 1
Forlimpopoli 1
Granarolo dell'Emilia e Viadagola 1
Libertyville 1
Los Angeles 1
Marzabotto 1
Nuoro 1
Osnago 1
Palermo 1
Pavia 1
Questembert 1
Reggio Calabria 1
Riolo Terme 1
Sagunto 1
San Nicola 1
Serra Riccò 1
Venezia 1
Vimodrone 1
Wilmington 1
Wuhan 1
Zhengzhou 1
Totale 992
Nome #
Monte Carlo with variance reduction in and around near-critical configurations 118
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 97
TAPIRO fast spectrum research reactor for neutron radiation damage analyses 74
Feasibility studies of an experimental campaign in TAPIRO devoted to the analysis of nuclear database for minor actinides 70
Learning Aspects of the Direct Statistical Approach to the Optimization of Monte Carlo Radiation Transport Calculations 70
Radiation transport out from the reactor core: To decouple or not to decouple 67
Calculation of the NEA-SINBAD Experimental Benchmark: PCA-Replica 66
Neutron-gamma flux and dose calculations in a Pressurized Water Reactor (PWR) 65
Sviluppo e applicazioni di metodologie Monte Carlo per le valutazioni neutroniche in supporto alle analisi di sicurezza dei reattori nucleari in operazione 60
Contractual Deliverable DS8 (WP4.1) Evaluation of Radiation Damage and Circuit Activation of the LBE-Cooled XADS 44
Monte Carlo Calculation of the Power Distribution in the PDS-xADS at BoL and EoL E. Nava, K. W. Burn - (FIS - NUC) 44
Comparison of integrated and decoupled Monte Carlo results outside PWR cores 41
State-of-the-Art of BNCT and FNT as at End 2006 and Relevance to Proposed ENEA Activities 41
MCNP Model OF The 1 MW TRIGA MARK II at ENEA CASACCIA 40
IRIS: Monte Carlo Results for Selected Ex-Core Radiation Responses. Restricted Version 40
Neutron-gamma flux and dose calculations in a pressurized water reactor (PWR) 39
Development and Application of Monte Carlo Neutronics Methodologies for Safety Studies of Current Operating Reactors 39
Evaluation of the Radiation Damage and Neutron Flux Spectra within the PDS-xADS Reactor at Bol 38
Alcuni risultati neutronici del nocciolo del reattore TAPIRO per un'indagine di danneggiamento strutturale 37
IRIS: Monte Carlo Results for Selected Ex-Core Radiation Responses. Open Version 37
Monte Carlo Methods for Core Safety Analysis: Design of Instrumentation for Monitoring PWR Core Degradation in case of a Severe Accident 37
Continuing Analysis with Monte Carlo Techniques of the Impact of the Heavy Reflector of a Typical Large Size GEN III+ Reactor Design on Some Safety Features: Completion of the Ex-Core Detector Calculations from PAR2010 and Examination ofthe Impact on the Phenomenon of Flux Tilt 37
Contractual Deliverable D49 (WP4.1) Core Reference Cycle Analysis far the LBE-Cooled XADS K. W. Burn, G. Glinatsis, E. Nava, V. Peluso, C. Petrovich, M. Sarotto, R. Tinti (FIS-NUC) 36
A correction and a clarification to "optimizing variance reduction in Monte Carlo eigenvalue calculations that employ the source iteration approach" 35
Development and Application of Monte Carlo Neutronics Methodologies for Safety Studies of Current Operating Reactors (Analisi neutronica con Metodi Monte Carlo di Impianti Nucleari Tipo PWR) 34
PDS-XADS Neutron Streaming in the Vacuum Tube and Doses from Neutron Activation in the Zone above the Roof 31
Use of Monte Carlo in State-of-the-Art PWR Design: Study of Tilt in the NEA UAM PWR Benchmark and Development and Testing of New Algorithms within Monte Carlo Eigenvalue Calculations employing the Source-Iteration Method 31
Development of Monte Carlo Algorithms for Eigenvalue – Calculations 31
Use of Monte Carlo to Evaluate Radiation Damage to Corium Detector in PWR Severe Accident Scenario 29
XADS WP4.1 D10 Appendix B: Assessment of the Possibility of Adopting Neutron Absorber or Moderator Elements to Reduce 210-Po Production 28
Optimizing variance reduction in Monte Carlo eigenvalue calculations that employ the source iteration approach This paper is dedicated to the memory of Lodovico Casalini (1955-2010) and of Carlo Artioli (1946-2014). 27
Totale 1483
Categoria #
all - tutte 6537
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 6537


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202037 0000 22 26 22129
2020/2021242 20108 573 021 1199031
2021/2022414 485713 344 2888 4816240
2022/2023790 621556496 43118 1971 10326330
Totale 1483