Ph.D., Nuclear Engineering, Iowa State University (1989)
M.S., Nuclear Engineering, Iowa State University (1986)
B.S., Metallurgical and Materials Engineering, Istanbul Technical University (1982)

Adjunct Professor, North-West University, South Africa, 2007-Today
Adjunct Professor, Bilkent University, 2005-Today
Associate Professor Dr., Department of Nuclear Engineering, Hacettepe University, 1993 - 2004
Assistant Professor Dr., Department of Nuclear Engineering, Hacettepe University, 1989 - 1993
Teaching and Research Assistant, Department of Nuclear Engineering, Iowa State University, 1984 - 1989

LIST OF PUBLICATIONS

Journal Articles

• O. O. Gülol, Ü. Çolak and B. Yıldırım, Performance analysis of TRISO coated fuel particles with kernel migration, Journal of Nuclear Materials 374, 168-177 (2008)

• S. Tanrıverdi, B. Mavis, G. Gündüz, and Ü. Çolak, Electrospinning and characterization of alumina borosilicate ceramic nanofibers, Materials 25, 957-968 (2007).

• U. Colak , Coupling strategies for desalination plants with gas cooled reactors, Int. J. Nuclear Desalination, Vol. 1, No.4, pp.427-434 (2005)

• U. Colak , V. Seker, Monte Carlo criticality calculations for a pebble bed reactor with MCNP,Nuclear Science and Engineering, v 149, (2005), 131-137

• R.S. Sen, Ü. Çolak, O.K. Kadiroğlu, “Nuclear Desalination with PBMR”, International Journal of Nuclear Desalination, 1 (2003), 271-279.

• O. Ö. Gülol, Ü. Çolak, “Comparison of pressure vessel integrity analysis and approaches for VVER1000 and PWR vessels for PTS conditions“ , Nuclear Engineering Design.226 (2003), 231-241.

• V. Şeker, Ü. Çolak, “HTR-10 First criticality analysis with MCNP”, Nuclear Engineering & Design, 222 (2003) 263-270.

• H. Akkurt, Ü. Çolak, “PWR system simulation and parameter estimation with neural networks”, Annals of Nuclear Energy , 2087 (29) 2002.

• Ü. Çolak , O. Özdere, “Comparative analysis of pressure vessel integrity for various LOCA conditions”, Journal of Nuclear Materials, 271 (297/3) 2001.

• H.H. Durmazuçar, Ü. Çolak, B. Sarıkaya, G. Gündüz, ' Burnup Characteristics and Performance of Boron Nitride and Boron Coated urania and urania-gadolinia fuel', Nuclear Engineering & Design, 203 (57) 2001.

• Z. Alper, Y. Bektur, Ü. Çolak, ‘The Floor Response Spectra for the Equipments Mounted to the Floors of a Reactor Building and Additional Safety Margins’, T. Jou. of Nucl. Sci., 22 (1995) 1.

• Ö. Gündüz, S. Köse, T. Akbaş, Ü. Çolak, ‘Analysis of WWER-440 Fuel Performance Under Normal Operating Conditions’, T. Jou. of Nucl. Sci., 22 (1995) 49.

• Ü. Çolak ve M. S. Wechsler, ‘Computer Simulation of Plastic Deformation in Irradiated Nb Single Crystals’, Tur. J. of Eng. and En Sci., 18 (1995) 45-53.

• U. Bezdegümeli, Ü. Çolak, C. Kocar, C. N. Sökmen, ‘Wigner Energy Calculations in the GHR20 Reactor’, Tur. J. of Eng. and Env. Sci., 17 (1993), 217-222.

Review Articles

• Ü. Çolak , ‘Industrial Applications of Radiation’, Physics Engineering Scientific and Technical Meeeting-4, 26-28 February 1992, Ankara. (Turkish)

Conference Presentations

International Conferences and Meetings

• B. Maviş, Ü. Çolak, T. Demirtaş, G. Gündüz, M. Gümüşderelioğlu, Bonelike apatitic calcium phospate sandwiched between electrospun polyacprolactone nanofiber mats: synthesis, characterization and osteoblastic activity, ECERS, 10th Internaational Conference of the European Ceramic Society, June 17-21 2007, Berlin, Germany.

• J. G. Hosking, T. D. Newton, O. Koberl, P. Morris, S. Goluoglu, T. Tombakoglu, U. Colak, E. Sartori, Analysis of an OECD/NEA High Temperature Reactor Benchmark, PHYSOR-2006, ANS Topical Meeting on Reactor Physics, Vancouver, B.C., Canada, 10-14 September 2006.

• Ü. Çolak , L. Brey, M. Methnani, Status of the IAEA Coordinated Research Project on HTGR Core Physics and Thermal Hydraulics Benchmarks (CRP5), Proccedding of HTR2006, 3rd ınternational Topical Meeting on High Temperature Reactor Technology, October1-4, 2006, Johannesburg, South Africa

• B. Kalpaklı, İ. Ö. Güler, Ü. Çolak, Ö. Gülsoy, Ş. L. Ergün, CFD Modeling of Hydrocyclone, International Mineral Processing Congress, Istanbul, Sept 2006.

• Ü. Çolak, V. Şeker, “Criticality Analysis of Pebble Bed Reactors with MCNP”, International Conference on Nuclear Mathematics and Computation (MC2003), 2-6 April 2003, Gatlinburg, TN, USA

• R.S. Sen, U. Colak, O.K. Kadiroglu,”Nuclear Desalination with PBMR”, International Conference on Nuclear Desalination, Challenges and Options, 16-18 October 2002, Marrakesh, Morocco.

• Ü. Çolak, “ Coupling Strategies for Desalination Plants with Gas Cooled Reactors”, International Conference on Nuclear Desalination, Challenges and Options, 16-18 October 2002, Marrakesh, Morocco

• A. T. Motta, R. A. Holt, Ü. Çolak, “Irradiation growth in zirconium at low temperatures by displacement cascade anisotropy”, 11th International Symposium on Reactor Dosimetry, 18-23 August 2002, Brussels, Belgium.

• Ü. Çolak , H. Dikmen, U. E. Sıkık, “Energy storage and release calculations for HTR-10 reflector” HTR-2002, April 2002, Petten Holland.

• Y. Cecen, Ü. Çolak, O. K. Kadiroğlu, “Burnup dependent core neutronic analysis for PBMR”, HTR-2002 April 2002, Petten, Holland

• Ü. Çolak , T. Akbaş, Ö. Gündüz, “Plutonium and burnup profiles in WWER-440 fuel at extended burnup”, presented in International Meeting on WWER Reactors Fuel Performance, Modelling and Experimental Support, October 2001, Varna, Bulgaria

• Y. Çeçen, A. Tongal, Ü. Çolak, O.K. Kadiroğlu, “Thorium Utilization and Burnup Characteristics of Pebble Bed Modular Reactor Fuel”, presented at Advanced Reactors with Innovative Fuel, ARWIF2001, October 2001, Glasgow, U.K.

• Ü. Çolak , A. B. Bölme, S. Köse, ‘Analysis of WWER-440 Fuel Performane with FRAPCON-3’, , I. Eurasia Conference on Nuclear Science and its Application, 23-27 October 2000, İzmir

• Ü. Çolak , ‘Nuclear Reactor Fuel Rod Behavior Modeling and Current Trends’, I. Eurasia Conference on Nuclear Science and its Application, 23-27 October 2000, İzmir

• Ü. Çolak , H. H. Durmazuçar, G. Gündüz, ‘A New Integral Fuel Burnable Absorber Design for LWR's’, 1997 International Topical Meeting on LWR Fuel Performance, Portland, Oregon, U.S.A.., March 2-6, 1997.

• İ. Uslu, Ü. Çolak, M. Tombakoğlu, G. Gündüz, ‘The Production, Characterization, and Neutronics Performance of Boron Nidride Coated Uranium Dioxide Fuel’, 4 th International Conference on CANDU Fuel, October 1-4, 1995, Pembroke Canada

• Ö. Gündüz, S. Köse, T. Akbaş, Ü. Çolak, ‘Analysis of WWER-440 Fuel Performance under Normal Operating Conditions'', International Meeting on WWER Reactors Fuel Performance, Modelling and Experimental Support, 7-11 November 1994, Varna, St. Constantine, Bulgaria.

• Ü. Çolak , O. K. Kadiroğlu, C. N. Sökmen, K. H. Hertzberger ve H. Schmitt, ‘Gas Cooled Reactor Application for a University Campus’, International Conference on Conventional and Nuclear District Heating, 18-22 Mart 1991, Lausanne, Switzerland, pp. 287-295.

National Conferences

1. S. Goluoğlu ve Ü. Çolak, ‘Gas cooled reactors and Turkey’s contribution and benefits’, Proceedings of the meeting “Nuclear Power Plants and Turkey”, January 22-23, 1990, Ankara, pp. 250-267. (Turkish)

• Ü. Çolak , ‘Effect of Electronic Stopping Cross Section on Radiation Damage Calculations’, The 5th National Congress of Nuclear Sciences, 22-24 May 1991, Izmir. (Turkish)

• U. Bezdegümeli, Ü. Çolak, C. Kocar, C. N. Sökmen, ‘Wigner Energy Deposition and Release in the Reflector of GHR-20’, The 5th National Congress of Nuclear Sciences, 22-24 Mayıs 1991, İzmir. (Turkish)

• Ü. Çolak , O. K. Kadiroğlu ve C. N. Sökmen, ‘Advanced Reactor Designs and Turkey’s Alternatives’, The 5th National Congress of Nuclear Sciences , 22-24 Mayıs 1991, İzmir. (Turkish)

• T. Bahadır, Ü. Çolak, O. K. Kadiroğlu ve C. N. Sökmen, ‘GHR20 Core Modelling’, The 5th National Congress of Nuclear Sciences , 22-24 Mayıs 1991, İzmir. (Turkish)

• İ. H. Arıkan, Ü. Çolak ve C. N. Sökmen, ‘Transient Modelling for GHR20 Reactor ’, The 5th National Congress of Nuclear Sciences, 22-24 Mayıs 1991, İzmir. (Turkish)

• Ü. Çolak , O. K. Kadiroğlu, C. N. Sökmen, Y. Sanalan, O. Zabunoğlu, ‘Heating Beytepe Campus with GHR-20’, The 5th National Congress of Nuclear Sciences , 22-24 Mayıs 19991, İzmir. (Turkish)

• Ü. Çolak , O. Zabunoğlu, K. Kavaklıoğlu, S. Lider, ‘Nuclear Reactor Alternative in Central Heating’, Physics Engineering, 37 (1992) 29-30. (Turkish)

• M. Ceyhan, Ü. Çolak, C. N. Sökmen, ‘Power Prediction in Nuclear Power Stations with Piecewise Linear Neural Networks’, The 6th National Congress on Nuclear Sciences, 18-20 September 1993, Bursa. (Turkish)

• Ü. Çolak , M. Sağlam, O. K. Kadiroğlu, ‘Neutronics Calculations for the Core of WWER 440 Reactor’, The 6th National Congress on Nuclear Sciences, 18-20 September 1993, Bursa. (Turkish)

• Z. Alper ve Ü. Çolak, ‘Two and Three Dimensional Pressure Vessel Modelling with ANSYS5.0 Finite Element Code’, The 6th National Congress on Nuclear Sciences, 18-20 September 1993, Bursa. (Turkish)

• A. Erdoğan ve Ü. Çolak, ‘Acceleration of Learning in Artificial Neural Networks and Applications to Nuclear Reactors’, The 6th National Congress on Nuclear Sciences, 18-20 September 1993, Bursa. (Turkish)

• H. Akkurt, Ü. Çolak, C. N. Sökmen, ‘Dynamic Modelling of a Pressurized Water Reactor’, The VII. National Congress on Nuclear Sciences and Technology, 3-6 September 1996, Istanbul. (Turkish)

• Z. Alper, Y. Bektur, Ü. Çolak, T. Akbaş, ‘Shear Stability of Containment Vessel during a Severe Eathquake’, The VII. National Congress on Nuclear Sciences and Technology, 3-6 September 1996, Istanbul. (Turkish)

• B. Sarıkaya, Ü. Çolak, M. Tombakoğlu, A. Yılmazbayhan, ‘Effect of Advanced Fuel Designs on Fuel Utilization’, pp. 271, National Symposium on Nuclear Fuel Technology, 3-5 September 1997, Çekmece Nuclear Research and Training Center, Istanbul. (Turkish)

• T. Akbaş ve Ü. Çolak, ‘Comparative Analysis of Fission Gas Release Models in Pressurized Water Reactor Fuel’, National Symposium on Nuclear Fuel Technology s. 261, , 3-5 September 1997, Çekmece Nuclear Research and Training Center, Istanbul. (Turkish)

• Ü. Çolak , ‘New Developments in Nuclear Fuel Technology, p. 23, National Symposium on Nuclear Fuel Technology, 3-5 September 1997, Çekmece Nuclear Research and Training Center, Istanbul. (Turkish)

• O.O.Gülol and Ü. Çolak, “Deterministic and Probabilistic Analysis of VVER-440 and VVER-1000 Reactor Presssure Vessel with Western Approach”, VIII. National Conress on Nuclear Science and Technologies, 15-17-October 2003, Kayseri, Turkey (Turkish)

• N. K. Şahin and Ü. Çolak, ”High Temperature Gas Cooled Reactor Fueal Particle’s Performance and Fission Product Behavior”, VIII. National Conress on Nuclear Science and Technologies, 15-17-October 2003, Kayseri, Turkey (Turkish)

• B. Mavis, T. T. Demirtaş, M. Gümüşderelioğlu, G. Gündüz and Ü. Çolak Polycaprolactone (PCL) Nanofibers Coated in a Calcium Phosphate Solution, Nano-TR-III, Nanobilim ve Nanoteknoloji Konferansı, Ankara, 11-14 Haziran 2007, Ankara

• E. Biber, G. Gündüz, Ü. Çolak ve B. Mavis, Effect of Process Parameters in Electrospinning of Polymeric Nanofibers, Nano-TR-III, Nanobilim ve Nanoteknoloji Konferansı, Ankara, 11-14 Haziran 2007, Ankara.

ThesIs AdvIsIng

Completed M.Sc. Thesis:

• M. Ceyhan, ‘Application of Neural Networks to Nuclear Power Systems'', M. Sc. Thesis, 1993.

• A. Erdoğan, ‘The Use of Neural Networks together with Fuzzy Logic Techniques in Nuclear Applications'', M. Sc. Thesis, 1993.

• Z. Alper, ‘The Dynamic Analysis of Nuclear Power Reactor Components’, M. Sc. Thesis, 1994.

• A. B. Bölme, ‘Analysis of Advanced Light Water Reactor Fuel Rod Performance’ M. Sc. Thesis 1996.

• H. Akkurt, ‘Development of a Control Model for a PWR’, M. Sc. Thesis 1996.

• B.Sarıkaya, ‘Advanced Integral Fuel Burnable Absorber Design and Fuel Management Calculations’, M. Sc. Thesis, 1999.

• O. Özdere, ‘Analyses of the Effects of Radiation Fluence and Impurity Content on the Fracture Mechanical Characteristics of Ferritic Pressure Vessel Steels’, M. Sc. Thesis, 2000

• F. Alim, ‘Finite Element Failure Analysis of Fuel Elements under Transient Conditions’, M. Sc. Thesis, 2000

• B.Ş. Güray, ‘Control Model Development for Components and System Simulation in a PWR’, M. Sc. Thesis, 2001.

• S. Şentürk, ‘Modeling of Irradiation Facilities with Monte Carlo Techniques’, M.Sc. Thesis 2002.

• N. K. Şahin,’High Temperature Gas Cooled Reactor Fuel Performance Analysis’, M.Sc. Thesis, 2003.

• N. Erkan,”Design amd optimization of Neutron Beam Prot for BNCT Applications”, M. Sc. Thesis, 2004.

• T. Yaşar, “Radiation Damage Calculations of VENUS Reactor Pressure Vessel with MCNP and SPECTER”, M.Sc. Thesis, 2005.

• G. Gökeri, “PBMR Monte Carlo Neutronics and Burnup Calculations”, M. Sc. Thesis, 2005.

• H. B. Aslan, “Integration of Condition Monitoring and Pattern Recognition Systems”, M. Sc. Thesis, 2005.

WORKSHOPS

1. IAEA Workshop on the status of HTGR technology - ICTP Center, Trieste, Italy (July 7-11, 2003)

2. IAEA Workshop on safety demonstration & market potential for High-Temperature Gas-Cooled Reactors, INET Institute, Tsinghua University, Beijing, China (Sep. 27-30, 2004)

3. Hacettepe University, Nanotechnology Workshop, June, 27-28, 2006.

4. Eurocourse on HTR Technology, IAEA and EU coordinated workshop, Petten, December 2007.

RESEARCH PROJECTS

P1. ‘Conversion of the UTR-10 Reactor at Iowa State University to Low-Enriched Fuel’, Iowa State University, Ames Iowa, U.S.A. 1988-1989.

P2. ''Calculation of Thorium Effective Cross Sections'', Turkish Atomic Energy Agency, TAEK-92-303-206-1994.

P3. ‘Dynamical Analysis of Reactor Components’, Turkish Atomic Energy Agency, 1994.

P4. Coordinated Research Project on Fuel Behavior at Extended Burnup (FUMEX), International Atomic Energy Agency (IAEA) 1995-1996.

1. Ü. Çolak, `FUMEX Practice with FRAPCON-2 Computer Code`, Coordinated Research Project (CRP) on the Fuel Behavior at Extended Burnup (FUMEX), Nisan 1996 Mumbai, India.

P5. ‘Development of a Control Model for a PWR’, H.U. Research Fund 95.01.010.018, 1996.

P6. ‘Design od Expert System and Neural Networks for Nuclear Reactor Core Design and Fuel Management’, H.U. Research Fund 95-01-010-012, 1998 .

P7. ‘Fuel Management in Boiling Water Reactors with Nonlinear Reactivity Model’, H.U. Research Fund 95-01-010-024, 1997.

P8. ‘Proposal for the Framework for the Preparation of Environmental Impact Statement for Nuclear Reactor and Guidelines’, Turkish Electricity Production and Transmission Company, TEAS-0063-Akkuyu, 1997.

P9. ‘Public Enlightment for Akkuyu Nuclear Power Plant and Nuclear Technology’, Turkish Electricity Production and Transmission Company, 1998

P10. ‘Development of Data Acquisition, Processing, and Control Devices for Radiation Detection’, Hacettepe University Research Fund 97-02-602-003, 1998.

P11. ‘Radiation Dose Measurement and Monte Carlo Simulation in Barite Concrete as Radiation Shielding’, Ado Mining Co., 2001.

P12. IAEA CRP-5 Coordinated Research Project on High Temperature Gas Cooled Reactors (Neutronics and CFD analyses for PBMR and HTR10)

IAEA TECDOC Evaluation of High Temperature Gas Cooled Reactor Performance (2003)

P13. BOTAŞ BTC Pipeline Construction Project, Ocuupational Health & Safety Training and Monitoring Services

P14. International Atomic Energy Agency, Coordinated Research Project, CRP-6, on HTGR Fuel.

Finite Element Thermal and Mechanical Analysis of HTR Fuel.

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