statistiche ricercatore

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

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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

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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

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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

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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

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	37	0	0	0	0	2	2	2	6	2	2	12	9
2020/2021	242	2	0	10	8	57	3	0	21	11	9	90	31
2021/2022	414	4	85	7	13	34	4	28	88	48	1	62	40
2022/2023	790	62	155	64	96	43	118	19	71	103	26	33	0
Totale													1483