Nahajate se v: | Reaktorska tehnika - R4 > Sodelavke in sodelavci > Leon Cizelj | En |
SI-1000 Ljubljana Slovenija Več
o Institutu Jožef Stefan
|
Kratek življenjepis Področja raziskav Mikromehanika Verjetnostna lomna mehanika Varnost kompleksnih tehnologi Varnost, zanesljivost, pregledovanje in vzdrževanje tlačnih posod in cevovodov z razpokami Staranje uparjalnikov v jedrskih elektrarnah Izobrazba Magister jedrske tehnike, Fakulteta za matematiko in fiziko, Jedrska tehnika, Univerza v Ljubljani, 1989 Univ. dipl. inženir strojništva, Fakulteta za strojništvo, Univerza v Mariboru, 1986 Nagrade 1994 Zlati znak Jožefa Stefana za doktorsko delo. Poučevanje Mehanika loma na podiplomski šoli za jedrsko tehniko (članica Združenja ENEN). Delovne izkušnje
Razvoj in uporaba tehnik verjetnostne lomne mehanike; Modeliranje s končnimi elementi (FAM) in analize (PAFEC-FE, ABAQUS) kompleksnih geometrij in nelinearnih materialov; Zagotavljanje kakovosti in standardizacija metode končnih elementov (NAFEMS); Tehniško svetovanje Nuklearni elektrarni Krško; Gost raziskovalec v Research Center Karlsruhe, Nemčija, Institute for Materials Research, 1.11.1993 - 30.4.1994; Sistemska administracija Unix in Windows delovnih postaj in manjših računalniških mrež Član komisije za aplikativno dejavnost pri Znanstvenem svetu Instituta "Jožef Stefan" (1996-2000); Član komisije Instituta "Jožef Stefan" za idustrijsko lastnino (1998-); Član komisije za metodologijo vrednotenja raziskovalnega dela pri Znanstvenem svetu Instituta "Jožef Stefan" (2005-). Član Znanstvenega sveta za tehni�ke vede pri Agenciji republike Slovenije za raziskave (ARRS 2006-2011) Članstvo v strokovnih združenjih Izbrane objave
Celotni sposek objav vzdržuje COBISS. Povezave na objave so pripravljene z uporabo Digital Object Identifier System DOI. I. Simonovski, B. Končar, L. Cizelj, Thermo-mechanical analysis of a DEMO divertor cooling finger under the EFREMOV test conditions, Fusion Engineering and Design 85 (2010) 130-137. [Preprint] L. Cizelj, M. Leskovar, M. Čepin, B.Mavko, A method for rapid vulnerability assessment of structures loaded by outside blasts, Nuclear Engineering and Design 239 (2009) 1641-1646. [Preprint] I. Simonovski, K.-F. Nillson, L. Cizelj, Microstructurally Small Cracks in 316L Steel and Their Dependance on Crystallographic Orientations of Grains, Fatigue and Fracture of Engineering Materials and Structures 20 (2007) 463-478. [Preprint] I. Simonovski, K.-F. Nillson, L. Cizelj, The Influence of Crystallographic Orientation on Crack Tip Displacements of Microstructurally Small, Kinked Crack Crossing the Grain Boundary, Computational Materials Science 39 (2007) 817-828. [Preprint] I. Simonovski, L. Cizelj, The Influence of Grains' Crystallographic Orientations on Advancing Short Cracks, International Journal of Fatigue 29 (2007) 2005-2014. [Preprint] G. Roussel, L. Cizelj, Reliability Of Sampling Inspection Schemes Applied To Replacement Steam Generators, Journal of Pressure Vessel Technology ASME 129 (2007) 109-117. [Preprint] M. Čepin, L. Cizelj, M. Leskovar, B. Mavko, Vulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices, Journal of Nuclear Science and Technology 43 (2006) 1258-1269. [Preprint] L. Cizelj, M. Leskovar, B. Končar,Vulnerability of a partially flooded PWR reactor cavity to a steam explosion, Nuclear Engineering and Design 236 (2006) 1617-1627. [Preprint] L. Cizelj, Probability Of Excessive Leak Rate Through Multiple Defects In Degraded Nuclear Steam Generator Tubes, Invited lecture at ICRESH-05, Mumbai, India (December 2005). M. Kovač, L. Cizelj, Modeling Elasto-Plastic Behavior of Polycrystalline Grain Structure of Steels at Mesoscopic Level, Nuclear Engineering and Design 235 (2005) 1939-1950. [Preprint] I. Simonovski, M. Kovač, L. Cizelj, Estimating the correlation length of inhomogeneities in a polycrystalline material, Mater. sci. eng., A Struct. mater. : prop. microstruct. process. 381 (2004) 273-280. [Preprint] M. Kovač, I. Simonovski, L. Cizelj, Vpliv zrnate strukture na elasto-plastini odziv polikristalnega skupka = The effect of grain structure on the elastic-plastic response of a polycrystalline aggregate, Strojnšiki vestnik 11 (2002) 580-590. L. Cizelj, H. Riesch-Oppermann, Early Development Of Stress Corrosion Cracks At The Grain Scale: Incomplete Random Tessellation Model, Nuclear Engineering and Design 212 (2002) 21-29. [Preprint] L. Cizelj, G. Roussel, Probabilistic evaluation of leak rates through multiple defects the case of nuclear steam generators, Fatigue and Fracture of Engineering Materials and Structures 26 (2003) 1069-1079. [Preprint] S. Weyer, A. Froelich, H.Riesch-Oppermann, L. Cizelj, M.Kovač, Automatic Finite Element Meshing of Planar Voronoi Tesselations, Engineering Fracture Mechanics 69 (2002) 945-958. [Preprint] L. Cizelj, H. Riesch-Oppermann, Modelling the Early Development of Secondary Side Stress Corrosion Cracks in Steam Generator Tubes Using Incomplete Random Tessellation, Nuclear Engineering and Design 212 (2002) 21-29. [Preprint] T. Dvoršek, L. Cizelj, B. Mavko, Safety and Availability of Steam Generator Tubes Affected by Secondary Side Corrosion, Nuclear Engineering and Design 185 (1998) 11-21. [Preprint] L. Cizelj, I. Hauer, G. Roussel, Ch. Cuvelliez, Probabilistic Assessment of Excessive Leakage through Steam Generator Tubes Degraded by Secondary Side Corrosion, Nuclear Engineering and Design 185 (1998) 347-359. [Preprint] L. Cizelj, H. Riesch-Oppermann, Stresses in the First Wall of a Dual Coolant Liquid Metal Breeder Blanket During Electron Beam Welding, Fusion Technology 32 (1997)14-22. [Preprint] L. Cizelj, B. Mavko, P. Vencelj, Reliability of Steam Generator Tubes with Axial Cracks, Journal of Pressure Vessel Technology 118 (1996) 441-446. [Preprint] L. Cizelj, B. Mavko, H.Riesch-Oppermann, A.Brckner-Foit, Propagation of Stress Corrosion Cracks in Steam Generator Tubes, Int J Press Ves & Piping 63 (1995) 35-43. [Preprint] L. Cizelj, B. Mavko, On the Risk-Based Steam Generator Lifetime Optimisation, Theoretical and Applied Fracture Mechanics 23 (1995) 129-137. [Preprint] L. Cizelj, B. Mavko, H. Riesch-Oppermann, Application of First and Second Order Reliability Methods in the Safety Assessment of Cracked Steam Generator Tubes, Nuclear Engineering and Design 147 (1994) 359-368. [Preprint]
|
Institut "Jo�ef Stefan", Odsek za reaktorsko
tehniko (R4), Jamova cesta 39, SI-1000 Ljubljana, Slovenija |