Assoc. Prof. Dr. Leon Cizelj
Head, Reactor Engineering Division
Jozef Stefan Institute
Jamova 39
SI-1000 Ljubljana
Slovenia
Phone: (+386) 1 5885 215
Fax: (+386) 1 5885 377
Email: leon.cizelj@ijs.si
More about the Institute
More about the Institute's reactor centre
More about physicist Jozef Stefan
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Biographical Sketch
- Born on January 1, 1964, in Celje. On the search for a proper profession (not to mention the sense of the life) I learned how to play clarinet and saxophone, spent some time by driving trucks, married Romana and became a father of two sons. Finally, I decided to become a mixture of a researcher and consultant in the exciting field of Nuclear Engineering. My spare time used to be divided between my family and playing clarinet and saxophone in a big band called �abe ( Frogs in
English). Recently, my family is very happy since I am spending my free
time with them. The Frogs are not so happy since I promised to make a
come back soon.
Research Interests
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Computational Structural Mechanics
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Micromechanics
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Probabilistic Fracture Mechanics
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Safety of Complex Technologies
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Safety, Reliability, Inspection and Maintenance of Crack-Containing
Structures
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Aging of Steam Generators in Nuclear Power Plants
Education
- Ph.D. in Physics, University of Ljubljana, Faculty of Mathematics and Physics, Nuclear Engineering Program, 1993
- M.Sc. in Nuclear Engineering, University of Ljubljana, Faculty of Mathematics and Physics, Nuclear Engineering Program, 1989
- B.Sc. in Mechanical Engineering, University of Maribor, Faculty of Mechanical Engineering, 1986
Awards
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1986 Kidri�'s award for students of University of Maribor (with Darko
Ogrizek)
- 1994 The Jo�ef Stefan Golden Emblem Prize Award for Ph. D. Thesis
Teaching
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Structural Mechanics
- Fracture Mechanics
at Graduate School for Nuclear Engineering (member of ENEN Association).
Professional Experience
- Since 1986 with Jo�ef Stefan Institute, Reactor Engineering Division. Professional
experience includes:
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- Development and application of probabilistic fracture mechanics techniques;
- Finite element modeling (FAM) and analysis (PAFEC-FE, ABAQUS) of complex geometries and nonlinear materials;
- Quality assurance and standardization in finite element methods (NAFEMS);
- System administration of Unix and Windows workstations and small networks;
- Member of Committee for Applied Research at Scientific Council of "Jo�ef Stefan" Institute (1996-2000);
- Member of Committee for Intelectual Property of "Jo�ef Stefan" Institute (1998-2002, 2002-2006, 2006-2010);
- Member of Committee for methodolgy of
research work appraisal at Scientific Council of "Jo�ef Stefan"
Institute (2005-).
- Member of the Scientific Council for Technology at the Slovenia Research Agency (ARRS).
Professional Societies
- Nuclear Society of Slovenia (NSS); Founding Member; Auditor 1996-1998; Board Member 1998-2002
- European Nuclear Society (ENS); Member Since 1991;
- American Society of Mechanical Engineers (ASME); Member Since 1995; Correspondent for Slovenia since 1997; Member of the District H operating Board
- Slovensko dru�tvo za mehaniko (Slovenian Society for Mechanics);Member Since 1988.
- SATENA (Slovenian Association of Technical and Natural Sciences); Member Since 2000, Board Member 2009-2011.
Selected Publications
See also complete list of publications available at COBISS.
Links to on-line publications are available through the Digital Object Identifier System DOI.
- L.
Cizelj, I. Simonovski, Microstructurally
Short Cracks in Polycrystalls Described by Crystal
Plasticity, Nova Science
Publishers, (in print 2010) . [Preprint]
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- I. Simonovski, B. Kon�ar, L. Cizelj, Thermo-mechanical analysis of a DEMO divertor cooling finger under the EFREMOV test conditions, Fusion Enginnering and Design 85 (2010) 130-137. [Preprint]
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- I. Simonovski, L. Cizelj, The influence of the grain structure size on microstructurally short cracks, ASME Engineering for Gas Turbines and Power 131(2009) 042903-1-042903-8. [Preprint]
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- L. Cizelj, M. Leskovar, M. �epin, B.Mavko, A method for rapid vulnerability assessment of structures loaded by outside blasts, Nuclear Engineering and Design 239 (2009) 1641-1646. [Preprint]
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- 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]
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- 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]
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- I. Simonovski, L. Cizelj, The Influence of Grains' Crystallographic Orientations on Advancing Short Cracks, International Journal of Fatigue 29 (2007) 2005-2014. [Preprint]
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- 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]
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- M. �epin, 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]
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- L. Cizelj, M. Leskovar, B. Kon�ar,Vulnerability of a partially flooded PWR reactor cavity to a steam explosion, Nuclear Engineering and Design 236 (2006) 1617-1627. [Preprint]
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- 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).
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- M. Kova�, L. Cizelj, Modeling Elasto-Plastic Behavior of Polycrystalline Grain Structure of Steels at Mesoscopic Level, Nuclear Engineering and Design 235 (2005) 1939-1950. [Preprint]
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- I. Simonovski, M. Kova�, 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]
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- M. Kova�, 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, Strojn�iki vestnik 11 (2002) 580-590.
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- 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]
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- 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]
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- S. Weyer, A. Froelich, H.Riesch-Oppermann, L. Cizelj, M.Kova�, Automatic Finite Element Meshing of Planar Voronoi Tesselations, Engineering Fracture Mechanics 69 (2002) 945-958. [Preprint]
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- 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]
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- T. Dvor�ek, 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]
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- 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]
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- 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]
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- L. Cizelj, B. Mavko, P. Vencelj, Reliability of Steam Generator Tubes with Axial Cracks, Journal of Pressure Vessel Technology 118 (1996) 441-446. [Preprint]
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- 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]
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- L. Cizelj, B. Mavko, On the Risk-Based Steam Generator Lifetime Optimisation, Theoretical and Applied Fracture Mechanics 23 (1995) 129-137. [Preprint]
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- 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]
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