NATIONAL TECHNICAL UNIVERSITY OF UKRAINE

“KIEV POLITECHNICAL INSTITUTE” AND ITS NUCLEAR EDUCATION PROGRAMS

M.Z. Zgurovskiy National Technical University of Ukraine “KPI”

Kyiv, Ukraine

E.N. Pis’mennyi National Technical University of Ukraine “KPI”

Kyiv, Ukraine

V.G. Razumovskiy National Technical University of Ukraine “KPI”

Kyiv, Ukraine

I.L. Pioro University of Ontario Institute of Technology

North Oshawa, Ontario, Canada

ABSTRACT

KPI ((http://www.ntu-kpi.kiev.ua/) is one of the oldest and biggest technical universities in Ukraine. It was founded in 1898.

Prof. D.I. Mendeleyev (inventor of the Periodic Table of Elements) was a chairman of the first examining board in KPI in 1903. World-famous are the names of I.I. Sikorskiy (Russian and American pioneer of aviation in both helicopters and fixed-wing aircraft), S.P. Timoshenko (the father of modern engineering mechanics), S.P. Korolyov (the lead Soviet rocket engineer and spacecraft designer), B.E. Paton (world-known Ukrainian metallurgist and specialist in welding technology), etc. who studied or worked in KPI.

Now KPI is the largest university in Ukraine - 28 000 students; 53 bachelor’s, 113 master’s, and 82 Ph.D. programs. 25 % of the students of the technical universities of Ukraine are the students of NTUU “KPI”. In 2011, more than 120 titles of scientific and educational literature were published and 17 scientific periodicals were issued at NTUU “KPI”.

KPI scientifically and technically cooperates with numerous international organizations and funds, such as: Ukraine-EU, Ukraine-NATO, International European Innovational Scientific and Technical Program “EUREKA”, IAEA, US Civilian Research and Development Foundation for Former Soviet Union countries (FSU), European Organization for Nuclear Research (CERN), Joint Institute for Nuclear Research (JINR), Organization of Black Sea Economic Cooperation (BSEC), Science and Technology Center in Ukraine (STCU), etc.

KPI is leading in preparation of the engineers for nuclear and thermal power plants in Ukraine. Its Heat Power Engineering Faculty includes two Departments to meet the challenge: the Department of Nuclear Power Plants and of Engineering Thermophysics and the Department of Heat-and-Power Engineering Units of Thermal and Nuclear Power Plants. The students learn such courses of Nuclear Engineering program as: Nuclear Power Unit Regulation; Erection, Maintenance, and Adjustment of Nuclear Power Units; Neutron-Physical Simulation of Reactors; NPP Reliability and Safety; Risk Management. Program of Engineering Thermophysics includes the following courses: Numerical Simulation of Thermal and Hydrodynamic Processes; Investigation of Alternative Energy Sources; Optimization of Power Equipment Operation, etc.

KEYWORDS: technical university, history, structure, cooperation, educational program.

Proceedings of the 2012 20th International Conference on Nuclear Engineering collocated with the

ASME 2012 Power Conference ICONE20-POWER2012

July 30 - August 3, 2012, Anaheim, California, USA

ICONE20-POWER2012-55265

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1. SHORT HISTORY AND OVERVIEW

KPI was founded in 1898. Prof. D.I. Mendeleyev

(inventor of the Periodic Table of Elements) was a chairman of the first examining board in KPI in 1903. World-famous are the names of I.I. Sikorskiy (Russian and then American pioneer of aviation in both helicopters and fixed-wing aircraft), S.P. Timoshenko (the father of modern engineering mechanics), S.P. Korolyov (the lead Soviet rocket engineer and spacecraft designer), B.E. Paton (world-known Ukrainian metallurgist and specialist in welding technology), etc., who studied or worked in KPI.

Initially it included 4 faculties. At present KPI has 21 faculties, 9 educational-and-research institutes, 12 R&D institutes (among them Institutes for Applied System Analysis and for Telecommunication Systems, Energy Saving & Energy Management Institute, Institutes of Physics & Technology, and Institute of Publishing & Printing Industry), and 14 scientific centers.

KPI scientifically and technically cooperates with numerous international organizations and funds, such as: Ukraine-EU, Ukraine-NATO, International European Innovational Scientific and Technical Program “EUREKA”, IAEA, US Civilian Research and Development Foundation for Former Soviet Union countries (FSU), European Organization for Nuclear Research (CERN), Joint Institute for Nuclear Research (JINR), Organization of Black Sea Economic Cooperation (BSEC), Science and Technology Center in Ukraine (STCU) supported by USA, Canada, and EU, International Center for Scientific and Technical Information (ICSTI).

In 2011 in KPI the International Forum for Peace and Mutual Understanding for Sustainable World Sake was held.

NTUU “KPI” is a basic center of Ukrainian Research and Academic Network (URAN).

The University has 23 academic buildings, 22 dormitories (hostels), sport palace, computerized library, culture center, kindergarten, 2 dining halls and recreation facilities (in the Black sea area), medical center for students, health center, student’s policlinic, 43 cafeterias.

2. HEAT POWER ENGINEERING

FACULTY. ITS NUCLEAR EDUCATION PROGRAMS

KPI is leading in preparation of the engineers for

nuclear and thermal power plants in Ukraine (the country constitutes a major nuclear player in Europe with 15 nuclear reactors in operation and 2 under construction). Heat Power Engineering Faculty of the University includes two Departments to meet the challenge: the Department of Nuclear Power Plants

and of Engineering Thermal Physics and the Department of Heat-and-Power Units of Thermal and Nuclear Power Plants.

University missions represent pre-university training (1 year), bachelor (4 years), master (2 years), Ph.D. (3 years), and post-diploma training. Undergraduate Nuclear Engineering programs provide such courses as: Nuclear Power Reactors; Theory of Nuclear Power Reactors; Atomic and Quantum Physics; Nuclear and Neutron Physics; Nuclear and Thermal Power Plants; Operation of Nuclear Units; NPP Mechanical Equipment; Pumping Equipment; Materials for NPP; Unsteady Processes in Nuclear Power Units; Emergency Processes in Nuclear Power Units; NPP Probability Risk Assessment; Safety Culture; Dosimetry; and other special courses.

The courses are in the first place delivered by highly prepared professionals, who have a wide experience in work at the NPPs (for many years as chief engineer at Byeloyarsk NPP, participated in commissioning fast breeder reactor BN-600, and shift engineer and disaster fighter at Chernobyl NPP) and have been trained, for example, in Idaho National Engineering Laboratory, USA. Some of the lecturers are invited (e.g., former graduates of KPI who now are Chief State Inspector and Deputy Chairman of the State Scientific and Technical Center of Nuclear Regulatory Commission).

They issued a series of textbooks (1 to 12) laid down in the basis of the main training courses.

Educational programs that are realized for more than decade virtually completely correspond to Multimedia educational course on Nuclear Reactor Physics developed by IAEA working group in 2011.

The Faculty established close links with state operating body – National Nuclear Power Generating Company Energoatom that helps in training, arranges annual contests of student’s scientific studies on power engineering in Ukraine, and sponsors International Summer Nuclear School.

During several years some of our students are invited to participate in a collaboration of about 450 physicists who are running a large particle detector at the electron-proton collider HERA (Hadron Elektron Ring Anlage) at the DESY (Deutsches Elektronen Synchrotron) laboratory in Hamburg. The ZEUS detector is a sophisticated tool for studying the particle reactions provided by the high-energetic beams of the HERA accelerator.

3. RESEARCH ACTIVITY High-level preparation of the students now is

impossible without both pre-graduation practical training which they undergo at the NPPs and their participation in research in the Laboratory of Heat Exchange and Diagnosis of Thermal-and-Physical

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Processes. The Laboratory was founded at the Heat Power Engineering Faculty in 1957 and has SCW experimental setup (Fig. 1) equipped with DC power supplying facilities that provide up to 1 MW for heating test sections and up to 180 kW to preheat 1 500 l/h of water treated in water purifier.

During the last four decades a series of the works concerning heat transfer and hydraulics of water, in particular, in 7-rod simulators of fuel bundles (Fig. 2) at under- and supercritical (up to 27.5 MPa) pressures, as well as in a gas-like state has been fulfilled. As a result, it was found that cooling of the vertical rods by supercritical water could take place both at normal and deteriorated heat transfer with a stable temperature profile along the heated length.

It has given the possibility to derive good approximations of the experimental data. The boundaries of heat-transfer transition into deteriorated mode accompanied by an abrupt wall temperature increase were obtained.

The results of these works were published, for example, in the Proceedings of four international

conferences on nuclear engineering (15 to 18). The experience accumulated for many years of the studies with respect to heat transfer in the fuel assemblies cooled by water under supercritical pressure has been assessed as enough to invite the representative of the Laboratory to participate in the IAEA Coordinated Research Project “Heat Transfer Behaviour and Thermohydraulics Codes Testing for Supercritical Water-Cooled Reactors”.

The Project evolves 10 countries developing the concept of Generation IV nuclear system, the main goals of which are to improve economic, enhance safety, extend sustainability, and strengthen proliferation resistance. In particular, the University is undertaking a Research Project entitled “Heat Transfer to Supercritical Water and Distribution of Local Thermal and Hydraulic Parameters of Single-Phase Flow in Vertical 7-Rod Bundle Simulators”, which forms part of the IAEA’s Coordinated Research Project.

Fig. 1. General schematic of the supercritical water experimental set-up: 1 electrical distillator; 2 ion exchanging filter; 3 accumulating reservoirs; 4 boosting pump; 5 plunger pumps; 6 and 7 regulating valves; 8 damping reservoirs; 9 turbine flowmeter; 10 heat exchanger; 11 electrical preheater; 12 dynamotor(s); 13 test section; 14 throttling valve; 15 damping reservoir; 16 insulating flanges; 17 main power supply; 18 cooler; 19 throttling valves.

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Fig. 2. Cross-section of the test section: 1 heated rod; 2 distancing rib; 3 shaped

dielectric displacer; 4 pressure tube. Some of the works, for example, on distribution

of local thermal and mass flow rate parameters of two-phase coolant in the bundle by using the method of isokinetic sampling (Fig. 3) are unique (13 and 14). Detailed pattern of flow in the bundle obtained in the experiments made it possible to find the most probable location of burnout in the cross-section of the bundle and to propose physical model of two-phase flow that comes to equivalent annular channel with eccentricity, whereas in the region of single-phase flow relation of mass flow rates in the cells is constant and quite well described by well-known correlation.

For many years scientific and technical basis for development, designing and implementation of high-performance passive heat-transferring evaporation-and-condensation systems for the objects of nuclear power technologies is being created (19). Within the framework of this program:

1. The state and development tendency of the systems of cooling, heat transfer, and thermal protection in nuclear power technologies were analyzed.

2. Subject to different limiting factors the heat transport ability of evaporation-and-condensation systems was studied.

3. The advantages of these systems were substantiated and the principal conditions of their thermal design were stated.

4. Thermal and engineering specification of numerous samples of evaporation-and-condensation systems of heat removal and thermal protection was experimentally obtained.

5. Circuit designs of evaporation-and-condensation systems of heat removal and thermal protection for various stages of nuclear power cycle were proposed. An example of such application is shown in Fig. 4.

For several decades one of the laboratories of the Heat Power Engineering Faculty is developing the methods and the facilities of dust suppressing, foam decontaminators, mixtures of surface-active substances, agents that convert radionuclides into soluble state, complex formers, and emulsifiers to make feasible contribution in decontamination of the territory of Chernobyl’ NPP.

Fig. 3. To the method of isokinetic sampling: 1 test section; 2 sampler; 3 sampling line; 4

flowrate control valve; 5 calorimetric cooler; 6 flowmeter; 7 pressure gauge lines; 8 differential pressure gauge; 9 cross section of sampling.

Fig. 4. System of passive emergency cooling of

reactor (19): 1 reactor vessel; 2 heat exchanger of

emergency cooling; 3 heat exchanger of intermediate circuit; 4 water storage tank; 5 connecting pipelines; 6 check valve; 7 discharge steam pipeline; 8 condensation chamber; 9 package of heat pipes; 10 evaporation sections of heat pipes; 11 condensation sections of heat pipes; 12 condensate pipeline; 13 pipeline; 14 containment.

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The results of all these investigations are used in

the educational program. Separate area in the studies of the Laboratory is

development of an automated diagnostic (expert) system to provide an improvement of operational reliability and safety of the fuel elements as the most thermally stressed components of water-cooled reactors due to timely recognition of the eve of dangerous heat-transfer modes by noise characteristics of operating parameters (neutron flux, dynamic pressure, coolant flow rate) continued 34 years. As a result, the doctoral thesis (20) was defended. It is based on the experiments (Fig. 5) in the Laboratory, at Rivne (VVER-440) and Chernobyl’ (RBMK-1000) NPPs, as well as both on the methods of up-to-date theory of artificial intelligence and on the methods of neuroinformatics using artificial neuron networks.

Fig, 5. Schematic diagrams of: (a) location of

rhodium detectors of neutron flux (DNF) in the central tube of fuel assembly; and (b) registration of neutron noise: 1 rhodium DNF; 2 measuring system; 3 magnetograph; 4 real-time spectrum analyzer Bruel&Kjaer-2133; 5 computer.

The results stated in the thesis were applied in

pilot intellectual diagnostic systems and were used for local verification of a number of basic physical models and correlations in state-of-the-art domestic and foreign thermal-and-hydraulic codes.

A cycle of the studies of thermoacoustic oscillations in heated channels with flowing inside supercritical water capable to destroy the channels was performed together with Chelyabinsk Polytechnic Institute (Russian Federation). The range of operating parameters of water, within which these

oscillations of pressure can occur, and the values of their amplitude and frequency for the tubes of the diameters close to hydraulic diameter of 7-rod bundles (e.g., 21) were obtained.

The majority of the works was executed in coordination with the leading scientific centers of the former Soviet Union (Kurchatov Institute of Atomic Energy, Dollezhal’ R&D Institute of Power Engineering, Institute of High Temperatures (Moscow); Institute of Physics and Power Engineering (Obninsk), OKBM (Nizhniy Novgorod), etc.).

4. REFERENCES

1. Shyrokov, S.V. Physics of Nuclear Reactors.

Textbook (in Russian), 2nd edition, VIPOL Publ. House, Kyiv, 1998, 288 p.

2. Shyrokov, S.V. Nuclear Power Reactors. Textbook (in Russian), 2nd edition, VIPOL Publ. House, Kyiv, 1997, 280 p.

3. Shyrokov, S.V. Transient Processes in Nuclear Reactors. Textbook (in Russian), VIPOL Publ. House, 2002, 286 p.

4. Byegun, V.V., Gorbunov, O.V., Kadenko, I.N., Pis’mennyi, E.N., Zenyuk, A.Yu., and Litvinskiy, L.L. Probability Risk Assessment of NPP. Textbook (in Russian), VIPOL Publ. House, Kyiv, 2000, 568 p.

5. Byegun, V.V., Byegun, S.V., Shyrokov, S.V., Kazachkov, I.V., Litvinov, V.V., and Pis’mennyi, E.N., Nuclear Security Culture in Ukraine”. Textbook (in Russian), VIPOL Publ. House, Kyiv, 2009, 363 p.

6. Nosovskiy, A.V., Vasil’chenko, V.N., Pavlenko, A.O., Pis’mennyi, E.N., and Shyrokov, S.V. Introduction into Safety of Nuclear Technologies (in Russian), Tekhnika Publ. House, Kyiv, 2006, 360 p.

7. Nosovskiy, A.V., Vasil’chenko, V.N., Klyuchnikov, A.A., and Yashchenko, Ya.V. Decomissioning of Nuclear Power Units (in Russian), Tekhnika Publ. House, Kyiv, 2005, 288 p.

8. Nosovskiy, A.V., Gavrish, V.M., Klyuchnikov, A.A., and Tkashyov, D.A. Decontamination (in Russian), Osnova Publ. House, Kyiv, 2009, 304 p.

9. Nosovskiy, A.V., Vasil’chenko, V.N., Klyuchnikov, A.A., and Prister, B.S. Chernobyl’ NPP Accident: Experience of Overcoming. Learned Lessons (in Russian), Tekhnika Publ. House, Kyiv, 2006, 264 p.

10. Nosovskiy, A.V., Alexeyeva, Z.M., and Borozenets’, G.P. Treatment of Radioactive Waste (in Ukrainian), Tekhnika Publ. House, Kyiv, 2007, 368 p.

11. Nosovskiy, A.V., Bogorad, V.I., Vasil’chenko, V.N., Klyuchnikov, A.A., Litvinskaya, T.V., and Slepchenko, A.Yu. Radiation Safety and Protection at Nuclear Power Plants (Monograph in Russian), Oberih Publ. House, Kharkiv, 2008, 356 p.

12. Nosovskiy, A.V. Safety of Life Activity, Politekhnika Publ. House, Kyiv, 2005, 288 p.

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13. Arkhipov, A.P., 1981. Research of

Distribution of Thermal and Hydraulic Parameters of Coolant in the Bundle of Cylindrical Fuel Rods. Cand. Sc. (Techn.) Thesis, Kyiv, 183 p. (in Russian).

14. Dalipagich, V.A., Mayevskiy, E.M., Razumovskiy, V.G., Pis’mennyi, E.N., Koloskov A.E., and Pioro I.L. On Distribution of Local Thermal and Mass Flow Rate Parameters of Two-Phase Coolant in the Bundle of 7 Rods. Proc. of the 20th Int. Conf. on Nuclear Engineering (ICONE20), Anaheim, Cal., U.S.A., July 30 – August 3, 2012, Paper 54140, 10 pages.

15. Pis’mennyi, E.N., Razumovskiy, V.G., Maevskiy E.M., Koloskov, A., Pioro, I. and Duffey, R., 2005. Experimental study on temperature regimes to supercritical water flowing in vertical tubes at low mass fluxes, Proc. of Int. Conf. GLOBAL-2005 “Nuclear Energy Systems for Future Generation and Global Sustainability, Tsukuba, Japan, October 9–13, Paper No. 519, 9 pages.

16. Pis’mennyi, E.N., Razumovskiy, V.G., Maevskiy Eu.M., Koloskov, A.Eu., and Pioro, I.L. Heat Transfer to Supercritical Water in Gaseous State or Affected by Mixed Convection in Vertical Tubes. Proc. of the 14th Int. Conf. on Nuclear Engineering (ICONE-14), Miami, FL., U.S.A., July 17–20, 2006, Paper 89483, 8 pages.

17. Razumovskiy, V.G., Pis’mennyy, Eu.N., Koloskov, A.Eu., and Pioro, I.L. Heat Transfer to

Supercritical Water in Vertical 7-Rod Bundle. Proc. of the 16th Int. Conf. on Nuclear Engineering (ICONE-16), Orlando, FL., U.S.A., May 11–15, 2008, Paper 48954, 6 pages.

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19. Gershuni, A.N., Nishchyk, A.P., and Pis’mennyi, E.N., 2007. Evaporation-and-Condensation Systems of Heat Transfer for Nuclear Power Technologies, Alterpress Publ. House, Kyiv, 236 p.

20. Sharayevskiy, I.G., 2009. Pattern Recognition of the Pre-Failure Thermal and Hydraulic Regimes in Water-Cooled Nuclear Power Reactors. Doctoral Sc. (Techn.) Thesis, Kyiv, 445 p. (in Russian).

21. Vetrov, V.I., Gerliga, V.A. and Razumovskiy, V.G., 1977. Experimental Study of Thermoacoustic Oscillations in Heated Channels at Supercritical Pressure of Water, (In Russian), The Problems of Nuclear Science and Technology, Section of Dynamics of the Nuclear Power Units, issue 2 (12), pp. 51-57.

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