Course on Natural Circulation Phenomena and Modelling in Water-Cooled Nuclear Reactors

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1 Activity SMR: 1848 Course on Natural Circulation Phenomena and Modelling in Water-Cooled Nuclear Reactors 25 June June 2007 Trieste - Total Number of Visitors: 36 Final List of Participants Updated: 28 June 2007

2 DIRECTOR Total number in this function: 3 1. CHOI Jong Ho REPUBLIC OF KOREA DIRECTOR 1. IAEA Nuclear Power Technology Development Section Division of Nuclear Power Dept. of Nuclear Energy Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna AUSTRIA 2. CLEVELAND John UNITED STATES OF AMERICA DIRECTOR 2. IAEA Nuclear Power Technology Development Section Division of Nuclear Power Dept. of Nuclear Energy Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna AUSTRIA 3. TUNIZ Claudio LOCAL ORGANIZER 3. Abdus Salam International Centre for Theoretical Physics Strada Costiera Trieste Page 2

3 Total number in this function: 8 4. AKSAN Nusret 2-PHASE FLOW, HEAT TRANSFER SWITZERLAND THERMAL-HYDRAULIC SAFETY ANALYSIS NUCLEAR REACTORS 4. Paul Scherrer Institut Dept. of Nuclear Energy/Safety Thermalhydraulics Lab., PSI 5232 Villigen SWITZERLAND 5. D'AURIA Francesco ACCIDENT ANALYSIS IN WATER-COOLED REACTORS NATURAL CIRCUL./STABILITY SINGLE & 2-PHASE FLOWS 5. Universita' degli Studi di Pisa Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione via Diotisalvi, Pisa 6. FERRERI Juan Carlos ARGENTINA 6. Autoridad Regulatoria Nuclear Gerencia Apoyo Cientifico Tecnico Av. del Libertador Buenos Aires ARGENTINA Page 3

4 7. HASSAN Yassin A. THERMAL-HYDRAULICS, CFD, MULTIPHASE FLOWS REACTOR SAFETY, ADV. NUCLEAR REACTORS, TURBULENCE UNITED STATES OF AMERICA 7. Texas A&M University Department of Nuclear Engineering Zachry 129 MS 3133 College Station TX UNITED STATES OF AMERICA 8. MARQUES Michel RELIABILITY ANALYSIS OF NUCLEAR COMPONENTS/SYSTEMS RELIABILITY OF NUCLEAR SAFETY PASSIVE SYSTEMS FRANCE 8. Commissariat a l'energie Atomique Centre d'etudes de Cadarache DEN, DER, SESI Bat 212 F Cedex St Paul Lez Durance FRANCE 9. REYES Jose N. UNITED STATES OF AMERICA 9. Oregon State University Nuclear Engineering and Radiation Health Physics 35th St. and Jefferson St. Corvallis OR UNITED STATES OF AMERICA Page 4

5 10. SAHA Dilip NUCLEAR REACTOR HEAT TRANSFER AND SAFETY PHENOMENA RELATED TO NATURAL CIRCULATION 10. Bhabha Atomic Research Centre Reactor Engineering Division Engineering Hall no Mumbai 11. VIJAYAN Pallippattu Krishnan 11. Bhabha Atomic Research Centre Thermal Hydraulics Section Reactor Engineering Division Trombay Mumbai Page 5

6 Total number in this function: ADORNI Martina 12. Universita' degli Studi di Pisa Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione via Diotisalvi, Pisa 13. APOSTOL Radu SAFETY ANALYSIS ROMANIA THERMALHYDRAULIC, CIRCUIT MODELATING & SIMULATION 13. CNE PROD Cernavoda NPP 1 Medgidiei Street P.O. Box Cernavoda Constanta ROMANIA 14. AWAISE Ahmed Sayed Mostafa NUCLEAR ENGINEERING EGYPT MODELING AND SIMULATION OF NUCLEAR POWER PLANTS 14. NPPA, Nuclear Power Plants Authority 4 El Nasr Avenue Nasr City P.O.B Abbasia Cairo EGYPT Page 6

7 15. BAJWA Mujahid Hussain PAKISTAN 15. Pakistan Institute of Nuclear Science and Technology Nuclear Power Engineering Reactor Division P. O. Box 3140 Nilore Islamabad PAKISTAN 16. BHATTACHARYYA Sati Nath REGULAR ASSOCIATE 16. Indian Institute of Technology Dept. Mechanical Engineering West Bengal Kharagpur 17. BUNITS Natalia RUSSIAN FEDERATION NC SYSTEMS IN ADVANCED DESIGNS ACCIDENT ANALYSIS FOR WWER TYPE REACTORS 17. FSUE EDO Gidropress 21, Ordzhonikidze str. Podolsk Moscow Dist. RUSSIAN FEDERATION Page 7

8 18. BURY Tomasz Piotr NUCLEAR POWER, HEAT TRANSFER, THERMODYNAMICS MODELING AND SIMULATIONS OF LOCA POLAND 18. Institute of Thermal Technology Silesian University of Technology 22, Konarskiego Str Gliwice POLAND 19. GARTIA Manas Ranjan MODELING OF NAT.CIRCUL.PHENOMENA, RELIAB.ANALYSIS RELIABILITY ASSESSMENT OF PASSIVE SYSTEMS 19. Bhabha Atomic Research Centre Reactor Engineering Division Engineering Hall no Mumbai 20. JHEETA Kuldeep Singh REGULAR ASSOCIATE 20. S.M.S. Medical College Dept. of Radiotheraphy Jaipur Rajasthan Page 8

9 21. JUARSA Mulya INDONESIA 21. BATAN, National Nuclear Energy Agency Center Reactor Technology and Nuclear Safety Thermal Hydraulics Laboratory PTRKN Building no. 80 Kawasan Puspiptek Complex, Serpong Tangerang Banten INDONESIA 22. KIM Hyoung-Tae THERMALHYDRAULICS, CFD ANALYSIS, PHWR SAFETY LOCA ANALYSIS, ZIRCALOY OXID., THERMAL RADIATION REPUBLIC OF KOREA 22. KAERI, Korea Atomic Energy Research Institute CANDU Safety Analysis Department Deokjin-Dong, Yuseong-Gu Daejeon REPUBLIC OF KOREA 23. MASCARI Fulvio THERMAL-HYDRAULIC CODE ASSESSM., BORON DILUTION INVEST. IN MID LOOP 23. Universita' degli Studi di Pisa Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione via Diotisalvi, Pisa Page 9

10 24. MELIDEO Daniele APPLIC. OF CFD TO REACTOR SAFETY ANALYSIS DOWNCOMER/LOWER PLENUM PHENOM. OF RPV 24. Universita' degli Studi di Pisa Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione via Diotisalvi, Pisa 25. MOHAN Joe SAFETY ANALYSIS OF NUCLEAR PLANTS 2-PHASE FLOW MODELING, STEAM GENERATOR PROCESS 25. Bhabha Atomic Research Centre Light Water Reactor Division Trombay Mumbai NANA Laurent REPUBLIC OF CAMEROON JUNIOR ASSOCIATE 26. University of Douala Faculty of Sciences Department of Physics P.O. Box Douala REPUBLIC OF CAMEROON Page 10

11 27. NYCH Nelia UKRAINE 27. Ministry of Fuel and Energy Department of Nuclear Energy and Atomic Industry Division of NPPs Operation and Technical Norms Khrestchatik st. 30 Kiev UKRAINE 28. OBED Rachel Ibhade NIGERIA JUNIOR ASSOCIATE 28. University of Ibadan Federal Radiation Protection Service Department of Physics Ibadan NIGERIA 29. PAKIDANSKI Valentin Slavchev BULGARIA 29. Kozloduy Nuclear Power Plant Power Production Units 5.6 Dep. of Reactor Technology 3321 Kozloduy BULGARIA Page 11

12 30. PARRONDO Ana Leticia TEHRMALHYDRAULICS IN PHWR REACTORS DETERMINISTIC SAFETY ANALYSIS ARGENTINA 30. Nucleoelectrica Argentina S.A., NASA Physics and Analysis Department Thermalhydraulic Section Arribenos 3619 Buenos Aires ARGENTINA 31. PHUNG Viet Anh SAFETY, TRANSIENT ANALYSIS ADV.PASSIVE SYST.REACT. SAFETY, ADVANCE REACTOR TECH., TRANSMUTATION VIET NAM 31. Royal Institute of Technology Division of Nuclear Power Safeety Alba Nova University Center Roslagstullbacken Stockholm SWEDEN 32. SADEK Sinisa MODELING & ANALYSIS OF SEVERE ACCIDENTS COOLING OF DEGRADED CORE DURING SEVER ACCIDENTS CROATIA 32. University of Zagreb Faculty of Electrical Engineering and Computing Department of Physics Unska Zagreb CROATIA Page 12

13 33. SODERHOLM Kristiina Katri FINAL SAFETY ANALYSIS REPORT FINLAND THERMALHYDRAULICS, TRANSIENT & ACCIDENT ANALYSIS 33. Teollisuuden Voima Oy FIN Olkiluoto FINLAND 34. TERZUOLI Fulvio CFD APPLIC. TO REACTOR SAFETY ANALYSIS DOWNCOMER/LOWER PLENUM PHENOM. OF RPV 34. Universita' degli Studi di Pisa Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione via Diotisalvi, Pisa 35. VALINCIUS Mindaugas THERMAL-HYDRAULICS LITHUANIA 2-PHASE FLOW EXPERIMENS, RELAP5 MODELLING 35. Lithuanian Energy Institute Breslaujos str. 3 LT Kaunas LITHUANIA Page 13

14 36. WIELENBERG Andreas THERMOHYDRAULICS IN NPP, PROB. SAFETY ANALYSIS REFLUX-CONDENSER & NAT. CIRCULATION IN PWR GERMANY 36. Gesellschaft Fur Reaktorsicherheit (G.R.S.) Mbh Forschungsgelande D-8046 Garching bei Munchen GERMANY Page 14

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