Andrej Prošek

Naziv delovnega mesta
Strokovno-raziskovalni svetnik

Institut
Jožef Stefan
Jamova cesta 39
SI-1000 Ljubljana
Slovenija

Telefon: +386 1 5885 358
Faks: +386 1 5885 377
E-pošta: andrej.prosek@ijs.si

Raziskovalna področja

• Jedrska varnost
• Deterministične varnostne analize (RELAP5, TRACE), animirane s programskim paketom SNAP (klikni za animacijo)
• Metode za oceno negotovosti realističnih programov (BEPU)
• Ocena natančnosti računalniških simulacij – izboljšana metoda na podlagi hitre Fourierjeve transformacije (FFTBM) z zrcaljenjem signalov
• Varnostne rezerve
• Varnostna kultura in sistem vodenja

Izobrazba

• Doktor znanosti s področja jedrske tehnike, Fakulteta  za matematiko in fiziko, Univerza v Ljubljani, 1999
• Magister  jedrske tehnike, Fakulteta  za matematiko in fiziko, Jedrska  tehnika, Univerza v Ljubljani, 1992
• Univ. dipl. inženir elektrotehnike, Fakulteta za elektrotehniko in računalništvo, Univerza v Ljubljani, 1987

Nagrade

• Priznanje ("Authors recognition") za prispevek z naslovom "LOCA PEAK CLADDING TEMPERATURE SENSITIVITY TO BREAK-SIZE AND PLUGGING LEVEL" na konferenci ANS Winter meeting, San Francisco, CA, 10-14. november 1991
• Nagrada za najboljše delo na XXXIII. konferenci ETAN v sekciji Nuklearna tehnika in tehnologija 1989

Delovne izkušnje

• Od 1987 sem zaposlen na Institutu "Jožef Stefan"
• Modeliranje in analize jedrskih naprav s sistemskima termohidravličnima računalniškima programoma RELAP5 in TRACE
• Razvoj in uporaba metod za določanje negotovosti izračunov s sistemskimi termohidravličnimi programi
• Tehniško svetovanje Nuklearni elektrarni Krško
• Odbor za varnost reaktorja TRIGA na IJS
• Sodelovanje v strokovnih odborih IAEA
• Sodelovanje v strokovnih odborih OECD/NEA

Izkušnje pri vodenju in upravljanju

• Vodenje več domačih in mednarodnih raziskovalnih projektov
• Slovenski koordinator za raziskovalni program CAMP od 2013
• Organizacija delavnice TRASNUSAFE februarja 2012 v Ljubljani
• Organizacija srečanja Spring 2012 CAMP v Ljubljani

ÄŒlanstvo v strokovnih združenjih

• Društvo jedrskih strokovnjakov Slovenije (DJS) (ustanovni član)
• European Nuclear Society

Izbrane objave

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

Knjige, poglavja v knjigah

KONÄŒAR, Boštjan, PROŠEK, Andrej, LESKOVAR, Matjaž. Surrogate model applied for analysis of uncertain parameters in turbulent mixing flows. V: IONESCU, Adela (ur.). Computational fluid dynamics : basic instruments and applications in science. Rijeka: InTech. 2018, str. 377- 396, doi: 10.5772/intechopen.70564.

RAIMOND, Emmanuel, DRIES, Gryffroy, PROŠEK, Andrej. Technological risk : nuclear accidents. V: POLJANŠEK, Karmen (ur.). Science for disaster risk management 2017 : knowing better and losing less, (EUR, ISSN 1831-9424, 28034 EN). [S. l.]: European Commission. cop. 2017, str. 356-366. http://drmkc.jrc.ec.europa.eu/portals/0/Knowledge/ScienceforDRM/Science%20for%20DRM%202017_version%2017%20May%202017.pdf.

PROŠEK, Andrej, LESKOVAR, Matjaž. Use of fast Fourier transform for sensitivity analysis. V: SALIH, Mohammed Salih (ur.). Fourier transform - signal processing and physical sciences. Rijeka: InTech, cop. 2015, str. 51-77.

PROŠEK, Andrej, ÄŒEPIN, Marko. Deterministic safety analyses for human reliability analysis. V: ROCHA, Claudio (ur.), AKUNE, Fernando (ur.), EL-SHAFIE, Ahmed (ur.). Artificial intelligence and hybrid systems. Hong Kong: IConcept Press, 2013, str. 73-109.

PROŠEK, Andrej, LESKOVAR, Matjaž. Application of fast Fourier transform for accuracy evaluation of thermal-hydraulic code calculation. V: NIKOLIĆ, Goran S. (ur.). Fourier transforms - approach to scientific principles. Rijeka: In-Tech, cop. 2011, str. 447-468.

ÄŒlanki v SCI revijah

VOLKANOVSKI, Andrija, PROŠEK, Andrej. Electric power frequency and nuclear safety : subsynchronous resonance case study. Nuclear Engineering and Technology, ISSN 1738-5733, [in press] 2019, 7 str., doi: 10.1016/j.net.2019.01.002.

PROŠEK, Andrej, KONÄŒAR, Boštjan, LESKOVAR, Matjaž. BEPU method applied to CFD simulation of mixing flows. Nuclear technology, ISSN 0029-5450, [in press] 2019, 15 str., doi: 10.1080/00295450.2018.1562820.

PROŠEK, Andrej, MATKOVIÄŒ, Marko. RELAP5/MOD3.3 analysis of the loss of external power event with safety injection actuation. Science and Technology of Nuclear Installations, ISSN 1687-6075, 2018, vol. 2018, str. 6964946-1-6964946-14, doi: 10.1155/2018/6964946.

PROŠEK, Andrej. RELAP5/MOD3.3 analyses of core heatup prevention strategy during extended station blackout in PWR. Energija, ISSN 0013-7448. [Print ed.], 2017, vol. 65, no. 3/4, str. 51-68.

PROŠEK, Andrej, KONÄŒAR, Boštjan, LESKOVAR, Matjaž. Uncertainty analysis of CFD benchmark case using optimal statistical estimator. Nuclear Engineering and Design : international journal devoted to the thermal, mechanical and structural problems of nuclear energy, ISSN 0029-5493. [Print ed.], 2017, vol. 321, str. 132-143, doi: 10.1016/j.nucengdes.2016.12.008.

PROŠEK, Andrej, VOLKANOVSKI, Andrija. RELAP5/MOD3.3 analyses for prevention strategy of extended station blackout. Journal of nuclear engineering and radiation science, ISSN 2332-8975, 2015, vol. 1, no. 4, str. 041016-1-041016-10, doi: 10.1115/1.4030834.

PROŠEK, Andrej, VOLKANOVSKI, Andrija. Extended blackout mitigation strategy for PWR. Nuclear Engineering and Design, ISSN 0029-5493. [Print ed.], dec. 2015, vol. 295, str. 360-373, doi: 10.1016/j.nucengdes.2015.09.030.

VOLKANOVSKI, Andrija, PROŠEK, Andrej. Delayed station blackout event and nuclear safety. Science and Technology of Nuclear Installations, ISSN 1687-6075, 2015, vol. 2015, str. 192601-1- 192601-9, doi: 10.1155/2015/192601.

PROŠEK, Andrej, LESKOVAR, Matjaž. Use of FFTBM by signal mirroring for sensitivity study. Annals of Nuclear Energy, ISSN 0306-4549. [Print ed.], 2014, vol. 76, str. 253-262, doi: 10.1016/j.anucene.2014.09.051.

MATKOVIÄŒ, Marko, CIZELJ, Leon, PROŠEK, Andrej. Characterization of a spent-fuel-pit rupture based on water-level monitoring. Annals of Nuclear Energy, ISSN 0306-4549. [Print ed.], jan. 2014, vol. 63, str. 674-679, doi: 10.1016/j.anucene.2013.09.002.

PROŠEK, Andrej, CIZELJ, Leon. Long-term station blackout accident analyses of a PWR with RELAP5/MOD3.3. Science and Technology of Nuclear Installations, ISSN 1687-6075, 2013, vol. 2013, str. 851987-1- 851987-15, doi: 10.1155/2013/851987.

VOLKANOVSKI, Andrija, PROŠEK, Andrej. Extension of station blackout coping capability and implications on nuclear safety. Nucl. Eng. Des.. [Print ed.], 2013, vol. 255, no. 1, str. 16-27, doi: 10.1016/j.nucengdes.2012.09.031.

PROŠEK, Andrej. RELAP5 Calculations of Bethsy 9.1b Test. Sci. Technol. Nucl. Install. (Print), 2012, vol. 2012, str. 238090-1-238090-11, doi: 10.1155/2012/238090.

PROŠEK, Andrej, BERAR, Ovidiu-Adrian. Advanced presentation of BETHSY 6.2TC Test results calculated by RELAP5 and TRACE. Sci. Technol. Nucl. Install. (Print), 2012, vol. 2012, str. 812130-1-812130-15, doi: 10.1155/2012/812130.

PROŠEK, Andrej, MAVKO, Borut. Animation model of Krško nuclear power plant for RELAP5 calculations. Nucl. Eng. Des.. [Print ed.], 2011, vol. 241, no. 4, str. 1034-1046.

PROŠEK, Andrej, MAVKO, Borut. RELAP5/MOD3.3 best estimate analyses for human reliability analysis. Sci. Technol. Nucl. Install. (Print), 2009, vol. 2009, str. 797193-1-797193-12.

PROŠEK, Andrej, ÄŒEPIN, Marko. Success criteria time windows of operator actions using RELAP5/MOD3.3 within human reliability analysis. J. loss prev. process ind., 2008, vol. 21, no. 3, str. 260-267.

PROŠEK, Andrej, LESKOVAR, Matjaž, MAVKO, Borut. Quantitative assessment with improved fast Fourier transform based method by signal mirroring. Nucl. Eng. Des.. [Print ed.], 2008, vol. 238, no. 10, str. 2668-2677.

PROŠEK, Andrej, MAVKO, Borut. RELAP5/MOD3.3 code validation with plant abnormal event : [selected papers from the International Conference Nuclear Energy for New Europe 2007, September 10-13, Portorož, Slovenia]. Sci. Technol. Nucl. Install. (Print), 2008, vol. 2008, str. 745178-1-745178-10.

PROŠEK, Andrej, MAVKO, Borut. The state-of-the-art theory and applications of best-estimate plus uncertainty methods. Nucl. technol., 2007, vol. 158, no. 1, str. 69-79.

PROŠEK, Andrej, D'AURIA, Francesco, RICHARDS, David J., MAVKO, Borut. Quantitative assessment of thermal-hydraulic codes used for heavy water reactor calculations. Nucl. Eng. Des.. [Print ed.], 2006, vol. 236, str. 295-308.

PROŠEK, Andrej, KVIZDA, Boris, MAVKO, Borut, KLIMENT, Tomáš. Quantitative assessment of MCP trip transient in a VVER. Nucl. Eng. Des.. [Print ed.], 2004, vol. 227, str. 85-96.

PROŠEK, Andrej, MAVKO, Borut. A tool for quantitative assessment of code calculations with an improved fast Fourier transform based method = Orodje za kvantitativno ocenitev računalniškega izračuna z metodo na podlagi hitre Fourirjeve transformacije. Elektrotehniški vestnik. [Slovenska tiskana izd.], 2003, letn. 70, št. 5, str. 291-296.

PROŠEK, Andrej, D'AURIA, Francesco, MAVKO, Borut. Review of quantitative accuracy assessments with fast Fourier transform based methods (FFTBM). Nucl. Eng. Des.. [Print ed.], 2002, vol. 217, str. 179-206.

PROŠEK, Andrej. Uncertainty evaluation of reactor safety parameters during SB LOCA. Trans. Am. Nucl. Soc., 2001, vol. 85, str. 148-149.

PROŠEK, Andrej, MAVKO, Borut. Evaluating code uncertainty-I : using the CSAU method for uncertainty analysis of a two-loop PWR SBLOCA. Nucl. technol., 1999, vol. 126, str. 170-185.

PROŠEK, Andrej, MAVKO, Borut. Evaluating code uncertainy-II : an optimal statistical estimator method to evaluate the uncertainties of calculated time trends. Nucl. technol., 1999, vol. 126, str. 186-195.

MAVKO, Borut, PROŠEK, Andrej, D'AURIA, Francesco. Determination of code accuracy in predicting small-break LOCA experiment. Nucl. technol., 1997, vol. 120, str. 1-19.

PETELIN, Stojan, MAVKO, Borut, PARZER, Iztok, PROŠEK, Andrej. RELAP5 post test calculation if IAEA-SPE-4. Trans. Am. Nucl. Soc., 1994, vol. 71, str. 537-538.

MAVKO, Borut, STRITAR, Andrej, PROŠEK, Andrej. Application of code scaling, applicability and uncertanity methodology to large break LOCA analysis of two-loop PWR. Nucl. Eng. Des.. [Print ed.], 1993, vol. 143, str. 95-109.

STRITAR, Andrej, MAVKO, Borut, PROŠEK, Andrej. Uncertanity analysis of the large break loss of coolant accident. Z. angew. Math. Mech., 1993, vol. 73, str. 918-920.

STRITAR, Andrej, MAVKO, Borut, PROŠEK, Andrej. The best-estimate analysis of LB LOCA with uncertanity evaluation. Trans. Am. Nucl. Soc., 1992, vol. 66, str. 584-585.

STRITAR, Andrej, MAVKO, Borut, PROŠEK, Andrej. LOCA peak clad temperature sensitivity to break size and plugging level. Trans. Am. Nucl. Soc., 1991, vol. 64, str. 681-682.

STRITAR, Andrej, PROŠEK, Andrej. The analysis of the reflood experiment. Z. angew. Math. Mech., 1991, vol. 71, str. 525-527.

PROŠEK, Andrej, MAVKO, Borut. Ocenjevanje natančnosti napovedi termohidravličnih programov = The accuracy quantification of thermal-hydraulic code. Stroj. vestn., 2003, letn. 49, št. 4, str. 218-229.

PROŠEK, Andrej, MAVKO, Borut. Določanje odzivne površine z optimalnim statističnim cenilnikom = Response surface generation with optimal statistical estimator. Stroj. vestn., 2000, letn. 46, št. 1, str. 14-23.

MAVKO, Borut, PROŠEK, Andrej. Termohidravlične varnostne analize v podporo zamenjavi uparjalnikov in povečanju moči v jedrski elektrarni Krško = Thermal-hydraulic safety analyses supporting the steam generator replacement and uprating at Krško nuclear power plant. Stroj. vestn., 2000, letn. 46, št. 4, 230-241.

Ekspertske misije

Predavatelj na delavnici Mednarodne agencije za atomsko energijo (MAAE)  Regional Workshop on Deterministic Safety Analysis for the Assessment of Safety Margins in NPP Design and Modifications, 23-27 March, 2009, Ljubljana, Slovenia. 2009.

Predavatelj na delavnici MAAE Regional Workshop on Quantification of Safety Margins, 22-26 September 2008, Portorož, Slovenia. 2008.

Predavatelj na delavnici MAAE  Regional Workshop on Application of Best Estimate plus Uncertainty (BEPU) Analysis, 10-14 March 2008, Budapest, Hungary. 2008.

Predavatelj na delavnici MAAE  Regional workshop on Safety analyses and technical support needed for power uprates, 24-28 September 2007, Ljubljana, Slovenia. 2007.

Predavatelj na delavnici MAAE  Regional Workshop on Utilization of Sefety Margins for Improved NPP Operational Flexibility, 21-25 May 2007, Budapest, Hungary. 2007. 

Predavatelj na delavnici MAAE  Regional Workshop on Deterministic Safety Analyses - Best Estimate plus Uncertainties for Design Basic Accidents, 2-6 April, 2007, Ljubljana, Slovenia. 2007.

Predavatelj na delavnici MAAE  Regional Workshop on Event, Transient and Precursor Analyses, 29 May - 2 June 2006, Budapest, Hungary. 2006.

Predavatelj na delavnici MAAE  Regional Workshop on Application of Deterministic Safety Analyses, 10-14 April, 2006, Ljubljana Slovenia. 2006.

Predavatelj na Regional Workshop RER/9/083 on Application of Deterministic Safety Analyses, Budapest, Hungary, 17 - 21 October 2005

Predavatelj na delavnici MAAE  Regional Workshop RER/9/083 on Deterministic Best Estimate Analyses including Uncertainties, 28th February - 4th March 2005, Ljubljana, Slovenia

Predavatelj na delavnici MAAE-TC Regional Workshop on Best Estimate Calculations Including Uncertainties, 19-23 April 2004, Ljubljana, Slovenia. 2004

Predavatelj na delavnici MAAE-TC Regional Workshop on Deterministic Safety Analyses (Safety Margins, Conservative vs. Best Estimate Analyses, Uncertainty Analyses, Validation and Verification of Codes), 5-9 May 2003, Ljubljana

Drugo

Mentor eni osebi na usposabljanju "Independent Evaluation of Modified Krško NPP Fuel Design", September 15 - December 15, 2016, JSI, Ljubljana.

Mentor dvema osebama na usposabljanju "Tutoring in the area of Regulatory requirements and safety evaluation of NPP SAR Part V – Technical Support Organization", August 17 – 21, 2015, JSI, Ljubljana.

Predavatelj na delavnici  Training Course "Requirements and safety evaluation for NPP SAR", July 6-11, 2015, Ljubljana, Slovenia. 2015.

Predavatelj na delavnici  EuroCourse 2, 7FP TRASNUSAFE EuroCourse, March 31 - April 2, 2014 Mol, Belgium. 2014.

Predavatelj na delavnici Training Course "Requirements and safety evaluation of PSA for NPP", May 20-24, 2013, Ljubljana, Slovenia. 2013.

Predavatelj na delavnici Design safety and safety evaluation for NPP - SAR: course documentation, training course, November 19-24, 2012, Institut Jožef Stefan, Ljubljana. 2012.