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Andrej Prosek

Senior Research Associate

Jožef Stefan
Institute
Jamova cesta 39
SI-1000 Ljubljana
Slovenia

Phone: +386 1 5885 358
Fax: +386 1 5885 377
E-mail: andrej.prosek@ijs.si

 

 

 

 

 

Research Interests

  • Nuclear Safety
  • Deterministic safety analysis (RELAP5, TRACE), animated with SNAP (click for animations)
  • Best Estimate Plus Uncertainty (BEPU) evaluation methodologies
  • Accuracy quantification of code predictions - improved Fast Fourier Transform Based Method (FFTBM) by Signal Mirroring
  • Safety Margins
  • Safety Culture and Management System

Education

Awards

  • Authors recognition for the technical paper entitled LOCA PEAK CLADDING TEMPERATURE SENSITIVITY TO BREAK-SIZE AND PLUGGING LEVEL presented at the ANS Winter Meeting, San Francisco, CA, November 10-14, 1991
  • Best work at XXXIII. ETAN conference in session Nuclear Technics and Technology, 1989

Professional Experience

  • Since 1987 employed by Jozef Stefan Institute
  • Validation and application of RELAP5 and TRACE system thermalhydraulic computer codes for safety analyses of nuclear installations
  • Development and application of best estimate plus uncertainty methods for uncertainty evaluation of system thermalhydraulic computer codes
  • Consulting to Nuklearna elektrarna Krško
  • Reactor safety committee of TRIGA reactor at Jožef Stefan Institute
  • Participation in the technical committees of the IAEA
  • Participation in the technical committees of the OECD/NEA

Management Experience

  • Since 1987 employed by Jozef Stefan Institute
  • Principal scientist of various domestic and international research projects
  • Coordinator for CAMP reserach program in Slovenia since 2013
  • Organiser of TRASNUSAFE workshop Ljubljana 2012
  • Organizer of Spring 2012 CAMP meeting in Ljubljana

Professional Societys

Selected Publications

The full list of publications is maintained by COBISS. Links to publications use the Digital Object Identifier System DOI.

Books, Chapters in Books

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, pp. 51-77.

PROŠEK, Andrej, ČEPIN, 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, pp. 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, pp. 447-468.

Articles in SCI Journals

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, pp. 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, pp. 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, pp. 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, pp. 253-262, doi: 10.1016/j.anucene.2014.09.051.

MATKOVIČ, 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, pp. 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, pp. 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, pp. 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, pp. 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, pp. 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, pp. 1034-1046.

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

PROŠEK, Andrej, ČEPIN, 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, pp. 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, pp. 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, pp. 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, pp. 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, pp. 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, pp. 85-96.

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, pp. 179-206.

PROŠEK, Andrej. Uncertainty evaluation of reactor safety parameters during SB LOCA. Trans. Am. Nucl. Soc., 2001, vol. 85, pp. 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, pp. 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, pp. 186-195.

MAVKO, Borut, PROŠEK, Andrej, D'AURIA, Francesco. Determination of code accuracy in predicting small-break LOCA experiment. Nucl. technol., 1997, vol. 120, pp. 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, pp. 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, pp. 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, pp. 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, pp. 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, pp. 681-682.

STRITAR, Andrej, PROŠEK, Andrej. The analysis of the reflood experiment. Z. angew. Math. Mech., 1991, vol. 71, pp. 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, pp. 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, pp. 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.

Expert assignments

Lecturer on IAEA Regional Workshop on Deterministic Safety Analysis for the Assessment of Safety Margins in NPP Design and Modifications, 23-27 March, 2009, Ljubljana, Slovenia. 2009.

Lecturer on IAEA Regional Workshop on Quantification of Safety Margins, 22-26 September 2008, Portoroz, Slovenia. 2008.

Lecturer on IAEA Regional Workshop on Application of Best Estimate plus Uncertainty (BEPU) Analysis, 10-14 March 2008, Budapest, Hungary. 2008.

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

Lecturer on IAEA Regional Workshop on Utilization of Sefety Margins for Improved NPP Operational Flexibility, 21-25 May 2007, Budapest, Hungary. 2007.

Lecturer on IAEA Regional Workshop on Deterministic Safety Analyses - Best Estimate plus Uncertainties for Design Basic Accidents, 2-6 April, 2007, Ljubljana, Slovenia. 2007.

Lecturer on IAEA Regional Workshop on Event, Transient and Precursor Analyses, 29 May - 2 June 2006, Budapest, Hungary. 2006.

Lecturer on IAEA Regional Workshop on Application of Deterministic Safety Analyses, 10-14 April, 2006, Ljubljana Slovenia. 2006.

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

Lecturer on IAEA Regional Workshop RER/9/083 on Deterministic Best Estimate  Analyses including Uncertainties, 28th February - 4th March 2005, Ljubljana,  Slovenia.

Lecturer on IAEA-TC Regional Workshop on Best Estimate Calculations Including Uncertainties, 19-23 April 2004, Ljubljana, Slovenia. 2004.

Lecturer on IAEA-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

Other

Tutor to one tutee on "Independent Evaluation of Modified Krško NPP Fuel Design", September 15 - December 15, 2016, JSI, Ljubljana.

Tutor to two tutees on "Tutoring in the area of Regulatory requirements and safety evaluation of NPP SAR Part V – Technical Support Organization", August 17 – 21, 2015, JSI, Ljubljana.

Lecturer on Training Course "Requirements and safety evaluation for NPP SAR", July 6-11, 2015, Ljubljana, Slovenia. 2015.

Lecturer on EuroCourse 2, 7FP TRASNUSAFE EuroCourse, March 31 - April 2, 2014 Mol, Belgium. 2014.

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

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

 

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Fall 2015 CAMP Meeting
CAMP (Code Applications and Maintenance Program) is the largest research program conducted under the auspices of the federal nuclear Administrative Commission of the US NRC (Nuclear Regulatory Commission) since 1993. In the context of the research prog...
MINOS International Workshop
Centre of excellence for nuclear materials - MINOS was established in 2011 by the Division of Atomic Energy, CEA, France. Within the Centre the basic and applied research in the field of nuclear materials and structures are carried out. The main object...
Hydrogen combustion in the experimental vessel
Reactor Engineering Division (R4) designed and executed hydrogen combustion experiment in the experimental device HYKA A2 at the Karlsruhe Institute of Technology (KIT) in 2012 with financial support from the European Commission. The most important res...
11th EUROfusion General Assembly meeting
European fusion research in the context of Horizon 2020 combines target-oriented 5-year (2014-2018) EUROfusion fusion program, which takes place under the auspices of the EURATOM treaty. The main objectives of the EU fusion...
Prof. Dr. Leon Cizelj will chair the program committee of the global nuclear conference ICONE24
International Conference on Nuclear Energy (ICONE) is one of the most renowned global conferences of nuclear experts working in industry, science, education and administrative bodies. The conference, at which over 1,000 participants from all over the w...
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