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Leon Cizelj

Vodja odseka
Znanstveni svetnik

Institut
Jožef Stefan
Jamova cesta 39
1000 Ljubljana
Slovenija

Telefon: (+386 1 5885 330)
Faks: (+386 1 5885 377)
E-pošta: Leon.Cizelj@ijs.si 

 

 

Raziskovalna področja

  • Varnost jedrskih objektov;
  • Varnost in zanesljivost kompleksnih tehnologij;
  • Celovitost in staranje za varnost pomembnih komponent jedrskih elektrarn;
  • Računalniška mehanika trdnin in tekočin;
  • Računalniška lomna mehanika;
  • Računalniška mikromehanika;
  • Računalniške večnivojske in večfizikalne metode.

Izobrazba

Nagrade

  • Kidričeva nagrada za študente Univerze v Mariboru (sonagrajenec Darko Ogrizek). 1986.
  • Zlati znak Jožefa Stefana za doktorsko delo. 1994.
  • Fellow, ameriško združenje strojnih inženirjev (ASME, American Society of Mechanical Engineers), 2016.

Poučevanje

Profesor za področje jedrske tehnike, Fakulteta za matematiko in fizikoUniverza v Ljubljani. Predmeti:

  • 2. bolonjska stopnja (magisterij):
    • Mehanika konstrukcij v jedrski tehniki (6 ECTS)
    • Lomna mehanika (6 ECTS)
  • 3. bolonjska stopnja (doktorat)
    • Mehanika jedrskih konstrukcij in materialov (10 ECTS)

Posnetki predavanj in oddaj

Delovne izkušnje

  • Razvoj in uporaba večnivojskih metod v mehaniki trdnin in lomni mehaniki;
  • Razvoj in uporaba metod verjetnostne lomne mehanike;
  • Modeliranje in analize kompleksnih geometrij in nelinearnih materialov s končnimi elementi (ABAQUS);
  • Zagotavljanje kakovosti in standardizacija metode končnih elementov (NAFEMS);
  • 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
  • Tehniško svetovanje Nuklearni elektrarni Krško;
  • Svetovanje Evropski komisiji (Generalni direktorat za raziskave in inovacije).
  • Svetovanje upravi za jedrsko varnost v ZDA (US NRC).
  • Sodelovanje v strokovnih odborih IAEA.
  • Sodelovanje v strokovnih odborih OECD/NEA.

Izkušnje pri vodenju in upravljanju

  • Predsednik upravnega odbora združenja ENEN (Evropsko združenje za izobraževanje na področju jedrske tehnike, združuje več kot 50 evropskih univerz in glavne jedrske deležnike: industrija, raziskave), 2016-2017, član 2010-2012 in 2015-2017.
  • Strateško in operativno vodenje Odseka za reaktorsko tehniko: raziskovalne skupine 30 raziskovalcev, ki deluje v mednarodnem okolju (2010-2013, 2014-2018).
  • Predstavnik Slovenije v posvetovalnem odboru Evropske komisije za jedrsko fisijo (CCE-FISSION, 2011-2013).
  • Član Znanstvenega sveta Instituta »Jožef Stefan« (2012-2013, 2014-2018).
  • Član znanstvenega sveta za tehniške vede pri ARRS (2006-2011, 2016-2021).
  • Predsednik Upravnega odbora ARAO (2013-2016).
  • Član upravnega odbora Evropske jedrske tehnološke platforme (SNETP, 2013-2015-2017).
  • Član komisije za izobraževanje Evropske jedrske tehnološke platforme (SNETP, 2010-2012-2015-2017).
  • Podpredsednik nadzornega sveta Gen Energija d.o.o. (2012-2013).
  • Podpredsednik nadzornega sveta ELES d.o.o. (2006-2008).
  • Član komisije za industrijsko lastnino Instituta »Jožef Stefan« (patenti, blagovne znamke, tehnične izboljšave…, od 1998 dalje).
  • Organizacija več mednarodnih znanstvenih konferenc.
  • Vodenje več mednarodnih raziskovalnih projektov.

Članstvo v strokovnih združenjih

  • Društvo jedrskih strokovnjakov Slovenije
    • Ustanovni član (1991)
    • Član upravnega odbora (1998-2002, 2006-2010).
    • Član nadzornega odbora (1996-1998).
  • Slovensko akademijsko tehniško in naravoslovno društvo SATENA
    • Član izvršilnega odbora (2009-2010, 2013-2015, 2015-2017).
    • Podpredsednik (2010-2011 in 2012-2013).
    • Predsednik (2011-2012).
  • Evropsko združenje jedrskih strokovnjakov ENS (European Nuclear Society), član »High Scientific Council« (2012-2016).
  • Ameriško združenje strojnih inženirjev ASME (American Society of Mechanical Engineers):

Urejanje

Urednik

Član uredniškega odbora

Izbrane objave

Celotni spisek objav vzdržuje COBISS. Povezave na objave so pripravljene z uporabo Digital Object Identifier System DOI.

ORCID: 0000-0002-8038-722X;
Scopus Author ID: 7004372090;
ResearcherID: A-3537-2008.

Knjige, poglavja v knjigah

CIZELJ, Leon, SIMONOVSKI, Igor. Microstructurally Short Cracks in Polycrystals Described by Crystal Plasticity, (Materials science and technologies). New York: Nova Science Publishers, cop. 2010. XII, 77 str., ilustr. (nekaj barv.). ISBN 978-1-61668-811-0. ISBN 1-61668-811-4.

SIMONOVSKI, Igor, CIZELJ, Leon. Grain-scale modeling approaches for polycrystalline aggregates. V: TODOROV ZACHARIEV, Zachary (ur.). Polycrystalline materials - theoretical and practical aspects. Rijeka: InTech, cop. 2011, str. 49-74.

CIZELJ, Leon, ROUSSEL, Guy. Reliability of degraded steam generator tubes. V: UCHANIN, Valentin (ur.). Steam generator systems : operational reliability and efficiency. Rijeka: In-Tech, cop. 2011, str. 117-142.

Članki v SCI revijah

EL SHAWISH, Samir, CIZELJ, Leon. Numerical investigation of grain misorientations at and close to the free surface of FCC polycrystalline metals. Computational materials science, 2016, vol. 113, pp. 133-142, doi: 10.1016/j.commatsci.2015.11.032.

GARRIDO, Oriol Costa, EL SHAWISH, Samir, CIZELJ, Leon. Uncertainties in the thermal fatigue assessment of pipes under turbulent fluid mixing using an improved spectral loading approach. International journal of fatigue,  2016, vol. 82, no. 3, pp. 550-560, doi: 10.1016/j.ijfatigue.2015.09.010.

CIZELJ, Leon. Research and higher education : a disposable part of fundamental national infrastructure. International journal of contemporary energy, 2015, vol. 1, no. 1, pp. 5-12, doi: 10.14621/ce.20150102.

GARRIDO, Oriol Costa, EL SHAWISH, Samir, CIZELJ, Leon. Stress assessment in piping under synthetic thermal loads emulating turbulent fluid mixing. Nuclear engineering and design, 2015, vol. 283, pp. 114-130, doi: 10.1016/j.nucengdes.2014.10.016.

SIMONOVSKI, Igor, CIZELJ, Leon. Cohesive zone modeling of intergranular cracking in polycrystalline aggregates. Nuclear engineering and design, 2015, vol. 283, pp. 139-147, doi: 10.1016/j.nucengdes.2014.09.041.

MATKOVIČ, Marko, CIZELJ, Leon, PROŠEK, Andrej. Characterization of a spent-fuel-pit rupture based on water-level monitoring. Annals of Nuclear Energy, 2014, vol. 63, pp. 674-679, doi: 10.1016/j.anucene.2013.09.002.

DRAKSLER, Martin, NIČENO, Bojan, KONČAR, Boštjan, CIZELJ, Leon. Large eddy simulation of multiple impinging jets in hexagonal configuration - Mean flow characteristics. International journal of heat and fluid flow, 2014, vol. 46, pp. 147-157, doi: 10.1016/j.ijheatfluidflow.2014.01.00.

VOLKANOVSKI, Andrija, CIZELJ, Leon. Nuclear power plant maintenance optimization with heuristic algorithm. Science and Technology of Nuclear Installations, 2014, vol. 2014, pp. 458016-1-458016-13, doi: 10.1155/2014/458016.

SIMONOVSKI, Igor, CIZELJ, Leon. Cohesive element approach to grain level modelling of intergranular cracking. Engineering fracture mechanics, 2013, vol. 110, pp. 364-377, doi: 10.1016/j.engfracmech.2013.05.011.

TISELJ, Iztok, ODER, Jure, CIZELJ, Leon. Double-sided cooling of heated slab : conjugate heat transfer DNS. International journal of heat and mass transfer, 2013, vol. 66, pp. 781-790, doi: 10.1016/j.ijheatmasstransfer.2013.07.076.

SIMONOVSKI, Igor, CIZELJ, Leon, GARRIDO, Oriol Costa. The influence of the grain boundary strength on the macroscopic properties of a polycrystalline aggregate. Nuclear Engineering and Design, 2013, vol. 261, pp. 362-370, doi: 10.1016/j.nucengdes.2012.12.007.

EL SHAWISH, Samir, CIZELJ, Leon, SIMONOVSKI, Igor. Modeling grain boundaries in polycrystals using cohesive elements : modeling grain boundaries in polycrystals using cohesive elements. Nuclear Engineering and Design, 2013, vol. 261, pp. 371-381, doi: 10.1016/j.nucengdes.2013.01.023.

GARRIDO, Oriol Costa, CIZELJ, Leon, EL SHAWISH, Samir. The role of the axial heat fluxes in the thermal fatigue assessment of piping. Nuclear Engineering and Design, 2013, vol. 261, pp. 382-393, doi: 10.1016/j.nucengdes.2013.01.024.

KOSTEVŠEK, Anja, CIZELJ, Leon, PETEK, Janez, PIVEC, Aleksandra. A novel concept for a renewable network within municipal energy systems. Renewable energy, I2013, vol. 60, pp. 79-87, doi: 10.1016/j.renene.2013.04.013. [

PROŠEK, Andrej, CIZELJ, Leon. Long-term station blackout accident analyses of a PWR with RELAP5/MOD3.3. Science and Technology of Nuclear Installations, 2013, vol. 2013, pp. 851987-1- 851987-15, doi: 10.1155/2013/851987.

TISELJ, Iztok, CIZELJ, Leon. DNS of turbulent channel flow with conjugate heat transfer at Prandtl number 0.01. Nucl. Eng. Des., 2012, vol. 253, pp. 153-160, doi: 10.1016/j.nucengdes.2012.08.008.

ORIOL, Costa, TISELJ, Iztok, CIZELJ, Leon. Depressurization of vertical pipe with temperature gradient modeled with WAHA code. Sci. Technol. Nucl. Install. (Print), 2012, vol. 2012, pp. 951923-1-951923-9, doi: 10.1155/2012/951923.

SIMONOVSKI, Igor, CIZELJ, Leon. Automatic parallel generation of finite element meshes for complex spatial structures. Comput. mater. sci., 2011, vol. 50, no. 5, pp. 1606-1618, doi: 10.1016/j.commatsci.2010.12.014.

SIMONOVSKI, Igor, CIZELJ, Leon. Computational multiscale modeling of intergranular cracking. J. nucl. mater., 2011, vol. 414, no. 2, pp. 243-250, doi: 10.1016/j.jnucmat.2011.03.051.

CIZELJ, Leon, SIMONOVSKI, Igor. Fatigue relevance of stratified flows in pipes : a parametric study. Nucl. Eng. Des., 2011, vol. 241, no. 4, pp. 1191-1195, doi: 10.1016/j.nucengdes.2010.03.030.

SIMONOVSKI, Igor, CIZELJ, Leon. Towards modeling intergranular stress corrosion cracks on grain size scales. Nucl. Eng. Des., 2012, vol. 246, pp. 107-114, doi: 10.1016/j.nucengdes.2011.08.032.

GARRIDO, Oriol Costa, CIZELJ, Leon, SIMONOVSKI, Igor. Modular 3-D solid finite element model for fatigue analyses of a PWR coolant system. Nucl. Eng. Des., 2012, vol. 246, pp. 115-122, doi: 10.1016/j.nucengdes.2011.06.038.

SIMONOVSKI, Igor, KONČAR, Boštjan, CIZELJ, Leon. Thermo-mechanical analysis of a DEMO divertor cooling finger under the EFREMOV test conditions. Fusion eng. des., 2010, vol. 85, no. 1, pp. 130-137, doi: 10.1016/j.fusengdes.2009.08.005.

SIMONOVSKI, Igor, CIZELJ, Leon, JAKŠIĆ, Nikola. The influence of finite element meshes on the results of a spatial polycrystalline aggregate model. Nucl. Eng. Des., 2011, vol. 241, no. 4, pp. 1184-1190, doi: 10.1016/j.nucengdes.2010.05.063.

SIMONOVSKI, Igor, NILSSON, Karl-Fredrik, CIZELJ, Leon. The influence of crystallographic orientation on crack tip displacements of microstructurally small, kinked crack crossing the grain boundary. Comput. mater. sci., 2007, vol. 39, no. 4, pp. 817-828, doi: 10.1016/j.commatsci.2006.10.005.

SIMONOVSKI, Igor, NILSSON, Karl-Fredrik, CIZELJ, Leon. Crack tip displacements of microstructurally small cracks in 316L steel and their dependence on crystallographic orientations of grains. Fatigue fract. eng. mater. struct., 2007, vol. 30, no. 6, pp. 463-478, doi: 10.1111/j.1460-2695.2007.01098.x.

SIMONOVSKI, Igor, CIZELJ, Leon. The influence of grains' crystallographic orientations on advancing short crack : [presented at Fatigue Damage of Structural Materials VI, The Sixth International Conference on Fatigue Damage of Structural Materials, 17-22 September 2006, Hyannis, MA, USA]. Int. j. fatigue, 2007, vol. 29, no. 9-11, pp. 2005-2014, doi: 10.1016/j.ijfatigue.2007.01.030.

ROUSSEL, Guy, CIZELJ, Leon. Reliability of sampling inspection schemes applied to replacement steam generators. J. press. vessel technol., 2007, vol. 129, no. 1, pp. 109-117, doi: 10.1115/1.2389027.

ČEPIN, Marko, CIZELJ, Leon, LESKOVAR, Matjaž, MAVKO, Borut. Vulnerability analysis of a nuclear power plant considering detonations of explosive devices. J. Nucl. Sci. Technol., 2006, vol. 43, no. 10, pp. 1258-1269, doi: 10.1080/18811248.2006.9711219.

CIZELJ, Leon, KONČAR, Boštjan, LESKOVAR, Matjaž. Vulnerability of a partially flooded PWR reactor cavity to a steam explosion. Nucl. Eng. Des., 2006, vol. 236, no. 10, pp. 1617-1627, doi: 10.1016/j.nucengdes.2006.04.018.

KOVAČ, Marko, CIZELJ, Leon. Modeling elasto-plastic behavior of polycrystalline grain structure of steels at mesoscopic level. Nucl. Eng. Des., 2005, vol. 235, pp. 1939-1950, doi: 10.1016/j.nucengdes.2005.05.009.

SIMONOVSKI, Igor, KOVAČ, Marko, CIZELJ, Leon. Estimating the correlation length of inhomogeneities in apolycrystalline material. Mater. sci. eng., A Struct. mater. : prop. microstruct. process., 2004, vol. 381, pp. 273-280, doi: 10.1016/j.msea.2004.04.046.

CIZELJ, Leon, ROUSSEL, Guy. Probabilistic evaluation of leak rates through multiple defects : the case of nuclear steam generators. Fatigue fract. eng. mater. struct., 2003, vol. 26, pp. 1069-1079, doi: 10.1046/j.1460-2695.2003.00692.x.

WEYER, Stefan, FROHLICH, Andreas, RIESCH-OPPERMANN, Heinz, CIZELJ, Leon, KOVAČ, Marko. Automatic finite element meshing of planar Voronoi tessellations. Eng. fract. mech., 2002, vol. 69, pp. 945-958, doi: 10.1016/S0013-7944(01)00124-2.

CIZELJ, Leon, RIESCH-OPPERMANN, Heinz. Modelling the early development of secondary side stress corrosion cracks in steam generator tubes using incomplete random tessellation. Nucl. Eng. Des., 2002, vol. 212, pp. 21-29, doi: 10.1016/S0029-5493(01)00474-5.

DVORŠEK, Tomaž, CIZELJ, Leon, MAVKO, Borut. Safety and availability of steam generator tubes affected by secondary side corrosion. Nucl. Eng. Des., vol. 185, pp. 11-21, doi: 10.1016/S0029-5493(98)00228-3.

CIZELJ, Leon, HAUER, Irena, ROUSSEL, G., CUVELLIEZ, C. Probabilistic assessment of excessive leakage through steam generator tubes degraded by secondary side corrosion. Nucl. Eng. Des., 1998, vol. 185, pp. 347-359, doi: 10.1016/S0029-5493(98)00229-5.

CIZELJ, Leon, RIESCH-OPPERMANN, Heinz. Stresses in the first wall of a dual-coolant liquid-metal breeder blanket during electron-beam welding. Fus. technol., 1997, vol. 32, pp. 14-22.

CIZELJ, Leon, MAVKO, Borut, VENCELJ, P. Reliability of steam generator tubes with axial cracks. J. press. vessel technol., 1996, vol. 118, pp. 441-446, doi: 10.1115/1.2842211.

CIZELJ, Leon, MAVKO, Borut, RIESCH-OPPERMANN, H., BRÜCKNER-FOIT, A. Propagation of stress corrosion cracks in steam generator tubes. Int. j. press. vessels piping, 1995, vol. 63, pp. 35-43, doi: 10.1016/0308-0161(94)00046-L.

CIZELJ, Leon, MAVKO, Borut. On the risk-based steam generator lifetime optimisation. Theor. appl. fract. mech., 1995, vol. 23, pp. 129-137, doi: 10.1016/0167-8442(95)00013-5.

CIZELJ, Leon, MAVKO, Borut, RIESCH-OPPERMANN, H. Application of first and second order reliability methods in the safety assessment of cracked steam generator tubing. Nucl. Eng. Des., 1994, vol. 147, pp. 359-368, doi: 10.1016/0029-5493(94)90218-6.

MAVKO, Borut, CIZELJ, Leon. Failure probability of axially cracked steam generator tubes : A probabilistic fracture mechanics model. Nucl. technol., 1992, vol. 98, pp. 171-177.

 

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