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List of Accepted Abstracts

The papers are listed in arrival order. The organizers are not responsible for the content of the papers. Pictures, tables, special characters and equations have not been converted for internet publishing. All details are available in the Book of abstracts.

 
  1. Damir Mandić - Slovenia
    Some Aspects of Digital I&C and Digital Human-System Interface Upgrades in Nuclear Power Plants

     

  2. Luka Štrubelj, Iztok Tiselj - Slovenia
    CFD Simulation of Kelvin-Helmholtz Instability

     


  3.  

  4. Dean Korošak, Bruno Cvikl, Janja Kramer, Renata Jecl, Anita Praprotnik, Miran Veselič - Slovenia
    Applications of Fractional Calculus to Diffusion Transport in Clay-Water System

     

  5. Vesna Benčik, Tomislav Bajs, Nenad Debrecin - Croatia
    RELAP5/MOD3.3 Analysis of the Reactor Coolant Pump Trip Event at NPP Krško for Different Transient Scenarios

     

  6. Sabina Markelj, Zdravko Rupnik, Iztok Čadež - Slovenia
    Detection System for Vibrational Spectroscopy of Hydrogen Molecules for Studies of Collision Processes in Fusion Edge Plasma

     

  7. Ivan Vrbanić, Johan Sörman - Croatia
    Framework for Ensuring Appropriate Maintenance of Baseline PSA and Risk Monitor Models in a Nuclear Power Plant

     

  8. Ivica Bašić, Davor Grgić - Croatia
    3D Simulation of a High Pressure Water Injection Into a Circular Cold Leg Pipe Flow

     

  9. Miroslav Babić, Ivo Kljenak, Borut Mavko - Slovenia
    Simulation of Atmosphere Mixing and Stratification in the ThAI Experimental Facility with a CFD Code

     

  10. Andrej Prošek, Iztok Parzer - Slovenia
    Accuracy Quantification of RELAP5 Predictions of NPP Events

     

  11. Tomaž Žagar, Joseph Magill - Slovenia
    Is Transmutation in an "Active" Repository Feasible?

     

  12. Matjaž Leskovar, Boštjan Končar, Leon Cizelj - Slovenia
    Simulation of Ex-Vessel Steam Explosion in PWR Reactor Cavity

     

  13. Andrej Prošek, Matjaž Leskovar - Slovenia
    Application of FFTBM to Severe Accidents

     

  14. Iztok Parzer, Ivo Kljenak - Slovenia
    ATWS Thermal-Hydraulic Analysis for Krško Full Scope Simulator Validation

     

  15. Andrej Prošek, Iztok Parzer - Slovenia
    SB LOCA Thermal-Hydraulic Analyses for Krško Full Scope Simulator Validation

     

  16. Iztok Parzer, Andrej Prošek - Slovenia
    Loss of Normal Feedwater Analyses for Krško Full Scope Simulator Validation

     

  17. Iztok Parzer, Boštjan Končar - Slovenia
    SGTR Analysis for Krško Full Scope Simulator Validation

     

  18. Robert Bergant, Iztok Tiselj - Slovenia
    Numerical Simulations of Turbulent Heat Transfer in a Channel at Prandtl Numbers Higher than 100

     

  19. Janez Gale, Iztok Tiselj - Slovenia
    Applicability of the Godunov's Method for Fundamental Four-Equations FSI Model

     

  20. Radko Istenič, Igor Jenčič - Slovenia
    Public Opinion About Nuclear Energy - Year 2005 Poll

     





  21. Ilija Plećaš - Serbia and Montenegro
    Leaching Study in Process of Solidification of Radionuclide 60CO in Concrete

     

  22. Lyubomir Pironkov, Slavka Tzanova - Bulgaria
    A European Project on Development of Training Courses for Personnel Involved in Decommissioning of Nuclear Installations

     

  23. Nikita Hristov, Valentin Papazov - Bulgaria
    Application of PSA Results for Prioritisation of Cable Penetrations Reinforcement from Seismic Point of View

     



  24. Nathalie Dessars - Belgium
    Extension of Severe Accident Management Guidelines to Shutdown and Low-Power Operation Modes Based on the WOG SAMG Approach

     

  25. Natalia Medvedeva, Andrey Andreev, Igor Peshkov, Vladislav Zhilko, Sergey Timkin - Russia
    Theoretical and Experimental Modeling of Processes Accompanying Single Fuel Channel (Pressure Tube) Rupture for RBMK Reactor. Parts B and C.

     

  26. Martin Kočan, R. Pánek, J.P. Gunn, Jan Stöckel, J.D. Skalný, Siegbert Kuhn, D. Tskhakaya - Slovak Republic
    Particle-in-Cell Simulations of the Segmented Tunnel Probe for Ion Temperature Measurements in the Tokamak Scrape-Off Layer

     



  27. John Emmett, Bob Smith - United Kingdom
    The Use of Modern Software Based Instrumentation in Safety Critical Applications

     

  28. Lidia Kinova, T. Grigorov, P. Nikolov, P. Petrova - Bulgaria
    Initial Radiological Activity Waste Categorization for Partial Dismantling of Research Reactor IRT- 2000, Sofia

     

  29. A. Nikiforova, Lidia Kinova, C. Peneva, P. Petrova - Bulgaria
    Preliminary Results from Uranium/Americium Affinity Studies under Experimental Conditions for Cesium Removal from NPP "Kozloduy" Simulated Wastes Solutions

     

  30. Gérard Ducros, Y. Pontillon, P.P. Malgouyres, P. Taylor, Y. Dutheillet - France
    Ruthenium Release at High Temperature from Irradiated PWR Fuels in Various Oxidising Conditions; Main Findings from the VERCORS Program

     



  31. Danut Bujoreanu, I.V. Popescu - Romania
    Measurement of the Leachability of Solidified Low - Level Radioactive Wastes Contaminated with C-14 Resulted from Cernavoda NPP

     

  32. Sayed Mohamad Hosseini, Kazuhisa Yuki, H. Hashizume, M. Tanaka - Japan
    The Three-Dimensional Study of Flow Mixing Phenomenon in a T-Junction Area with 90-Degree Bend Upstream

     

  33. Norbert Jakobs, Rudolf Baumgartl - Germany
    Visual Inspection, Better Than Your Eyes

     

  34. Dino Araneo, Alessandro Del Nevo, Francesco D'Auria, Giorgio Maria Galassi - Italy
    Scaling of Small Break LOCA in VVER 1000 System

     

  35. Patrice Giordano, Luis E. Herranz, Tim Haste, Jean-Claude Micaelli - France
    SARNET: Severe Accident Research Network Key Issues in the Area of Source Term

     

  36. Martin Kropík, Monika Juŕičková, Karel Matějka - Czech Republic
    New Digital Control and Power Protection System of VR 1 Training Reactor

     



  37. Norbert Jakobs, Rudolf Baumgartl - Germany
    Appearances can be Deceptive, Innovative Laser Profilometry Enhances Your Safety

     

  38. Christian Mun, Laurent Cantrel, Charles Madic - France
    Study of the Ruthenium Fission-Product Behaviour in the Containment of a Nuclear Reactor, in Case of a Severe Accident Occurring in Oxidant Conditions

     





  39. Carmen Varlam, Ioan Stefanescu, Vasile Petrascu, Cristina Bucur, Mihai Varlam, Mircea Raceanu, Adrian Enache, Ionut Faurescu - Romania
    The NPP Cernavoda Use to Estimate Maximum Soluble Pollutants Concentration on Danube Black Sea Channel

     

  40. Mirela Nitoi, Margarit Pavelescu, Ilie Turcu, Gheorghe Florescu, Minodora Apostol, Mita Farcasiu - Romania
    Ageing Effects Modelling in Probabilistic Safety Assessment of Nuclear Power Plants

     

  41. V. Vrtílková, L. Novotný, V. Hamouz, Robert Doucha, Ivan Tinka, J. Macek, F. Lahovský - Czech Republic
    Practical Illustration of the Traditional vs. Alternative LOCA Embrittlement Criteria

     

  42. V. Balaceanu, Viorel Hristea - Romania
    Study of the End Flux Peaking for the CANDU Fuel Bundle Types by Transport Methods

     



  43. Lubor Žežula - Czech Republic
    Method of Public Support Evaluation for Advanced NPP Deployment

     

  44. Flavio Parozzi, S. Chatzidakis, T. Gelain, Luis E. Herranz, E. Hinis, Christos Housiadas, Christophe Journeau, E. Malgarida, G. Nahas, Pascal Piluso, William Plumecocq, Jacques Vendel - Italy
    Investigation on Aerosol Transport in Containment Cracks

     

  45. Algirdas Kaliatka, Mindaugas Vaisnoras - Lithuania
    Simulation of Water Hammer Experiments Using RELAP5 Code

     



  46. I.A. Lipatov, I.V. Elkin, A.I. Antonova, G.I. Dremin, A.V. Kapustin, S.M. Nikonov, A.A. Rovnov, V.I. Gudkov - Russia
    Four-Quadrant Characteristics of PSB-VVER Pumps

     

  47. Gabriel Farkas, Vladimír Slugeň, Peter Domonkoš - Slovak Republic
    Nuclear Analysis of the EUROFER 97 Alloy by MCNP-4C2 Code

     

  48. Vladimír Slugeň, Vladimir Krsjak - Slovak Republic
    Non-Destructive Evaluation of WWER-Class RPV Steels

     

  49. Ján Mikuš - Czech Republic
    Fuel Pin Bowing and Related Investigation of WWER-440 Control Rod Influence on Power Release Inside of Neighbouring Fuel Pins

     



  50. Stanislovas Ziedelis, Algirdas Kaliatka, Viktor Ognerubov, Arvydas Adomavicius - Lithuania
    Analysis of the RBMK-1500 Type Reactor Emergency Core Cooling System Behavior, Taking into Account the Specified Hydraulic Characteristics of Fast Acting Motor Valves

     

  51. Evgeny Kapralov - Russia
    Refresher Training as an Important Factor Affecting Safety of Atomic Energy Utilization Facilities

     

  52. Kyoo Hwan Bae, H.C. Kim, Sung-Quun Zee, B.D. Chung, S.H. Kim - Korea, Republic
    SBLOCA Analysis for the Long Term Cooling Plan of 65 MWt Integral Reactor

     

  53. Mihai Culcer, Mariana Iliescu, Marian Curuia, Adrian Enache, Mircea Raceanu, Ioan Stefanescu, Catalin Ducu, Viorel Malinovschi - Romania
    Automatic System for Tritium Contaminated Surface Monitoring

     

  54. Mariana Iliescu, Mihai Culcer, Marian Curuia, Mircea Raceanu, Adrian Enache, Ioan Stefanescu - Romania
    Development of a Deuterium Separation Factors in Palladium-Hydrogen Systems Measurement Method in Order to Evaluate the Tritium Separation

     

  55. Sofia Carlos, Enrico Zio - Spain
    Detection of Malfunctions in the Secondary System of a Nuclear Power Plant by Neural Networks

     

  56. Thomas Frank, Philip Zwart, Junmei Shi, Eckhard Krepper, Dirk Lucas, Ulrich Rohde - Germany
    Inhomogeneous MUSIG Model - A Population Balance Approach for Polydispersed Bubbly Flows

     



  57. Monsefi Mehrdad, Nilforooshan Behnam, Hojabri Alireza, Nima Vaziri - Iran
    Study of Chemical Precipitation of Cs

     

  58. Tino Liebschner, Burkhard Heidowitzsch - Germany
    Advanced Digital I&C Technology in Nuclear Power Plants - A Success Story from Finland and China

     



  59. Martina Adorni, Anis Bousbia Salah, Francesco D'Auria, Rahim Nabbi - Italy
    Analysis of Typical Loss of Core Cooling and Positive Reactivity Insertion Transients in the FRJ-2 D2O Tank Type Research Reactor

     

  60. Tewfik Hamidouche, Anis Bousbia Salah, Martina Adorni, Francesco D'Auria - Italy
    Analysis of Loss of Coolant Accident in MTR Pool Type Research Reactors

     

  61. Jose F. Villanueva, Sofia Carlos, Sebastián Martorell, V. Serradell, F. Pelayo, R. Mendizábal, C. Cirauqui, I. Sol - Spain
    Study of the Impact on PSA Success Criteria of the Variability of the Initial Liquid Level in Case of the Loss of the RHR System Accident Scenario Under Mid-Loop Operating Conditions

     

  62. Hans Helmut Over, Erik Wolfart, Claude Ives Rieg - Netherlands
    The Material and Document Management Databases of JRC Petten - Useful Tools for European Nuclear Society

     

  63. Gabriel Farkas, Vladimír Slugeň, Peter Ballo - Slovak Republic
    Monte Carlo Calculation of the Spatial Weighting Function of Ex-Core Detectors for the WWER-440 Reactor Using MCNP-4C2 Code

     

  64. Juozas Augutis, Inga Zutautaite - Lithuania
    Estimation of Parameters in Ageing Model Using Bayesian Approach

     

  65. Johan Sörman - Sweden
    Evaluation of Test Intervals Strategies with the Use of Risk Monitor

     

  66. Pascal Piluso, Eric Boccaccio, Jean-Michel Bonnet, Christophe Journeau, Pascal Fouquart, Daniel Magallon, Ivan Ivanov, Ivan Mladenov, Stoyan Kalchev, Pavlin Groudev, Matjaž Leskovar, Hans Alsmeyer - France
    Severe Accident Experiments on PLINIUS Platform: Results of First Experiments on COLIMA Facility Related to VVER-440, Presentation of Planned VULCANO and KROTOS Tests

     

  67. Roberto Passalacqua, Jordanka Georgieva, Antoaneta Stefanova, Pavlin Groudev, Polina Tusheva, Ivan Mladenov, Dimitar Dimov - Italy
    Comparison of ASTEC & MELCOR Calculations in Case of SBLOCA for VVER-1000 Reactor

     

  68. George Bereznai, William Garland - Canada
    The Role of Universities in Managing Canada's Nuclear Knowledge

     

  69. Gheorghe Negut, Ilie Prisecaru - Romania
    RIA Type Tests Model Modeled with RELAP5-SCDAP

     



  70. J. Zmitkova, C.M. Allison, J.K. Hohorst - Czech Republic
    Application of RELAP/SCDAPSIM/MOD3.4 for Czech Republic Research Reactor Applications

     





  71. Reza Jafarian, Kamran Sepanloo - Iran
    Human Reliability Analysis for Steam Generator Feed-and-Bleed Accident in Bushehr NPP-1

     

  72. Claire Blackett, Joe Carthy, Anne Drummond, John Dunnion - Ireland
    Combining Accident Analysis Methods for Organisational Safety

     

  73. Roman Schrittwieser, Codrina Ioniţă, Petru Balan, Carlos Varandas, Humberto Figueiredo, C. Silva, Jan Stöckel, Jiří Adámek, Martin Hron, Milan Tichý, C. Hidalgo, M.A. Pedrosa, E. Calderón, Emilio Martines, Guido Van Oost, J.P. Gunn, T. Klinger - Austria
    Edge Plasma Fluctuations Measurements in Fusion Experiments

     



  74. Codrina Ioniţă, Roman Schrittwieser, Petru Balan, Jan Stöckel, Jiří Adámek, Martin Hron, Carlos Varandas, Humberto Figueiredo, C. Silva, Milan Tichý, Emilio Martines, Guido Van Oost, J.P. Gunn, T. Klinger - Austria
    Probe Diagnostics for Edge Plasmas in Fusion Experiments

     

  75. Ernst-Arndt Reinecke, Joerg Boehm, Pere Drinovac, Stephan Struth, Inga Maren Tragsdorf - Germany
    Modelling of Catalytic Recombiners: Comparison of REKO-DIREKT Calculations with REKO-3 Experiments

     

  76. György Hegyi, Gábor Hordósy - Hungary
    The Results of Comparison of Benchmark Calculations for Hexagonal Lattices with Different Methods

     

  77. György Hegyi, András Keresztúri, Istvan Trosztel - Hungary
    Selected Examples for Safety Analysis in VVER-440 Type Reactors Simulated by the Coupled ATHLET/KIKO3D Code System

     

  78. Radim Briš - Czech Republic
    RCM Optimization of a Distribution System under both Preventive and Corrective Maintenance

     



  79. Péter Windberg, E. Perez-Feró - Hungary
    Mechanical Test of E110 Cladding Material Oxidized in Hydrogen Rich Steam Atmosphere

     

  80. Eckhard Krepper, Alexander Grahn - Germany
    Numerical Investigations for Insulation Particle Transport Phenomena in Water Flow

     

  81. Ari Auvinen, Ulrika Backman, Jorma Jokiniemi, Martin Kissane, Mihály Kunstár, Maija Lipponen, Imre Nagy, Nóra Vér, Riitta Zilliacus - Finland
    Investigations on Ruthenium Transport in Highly Oxidising Conditions

     



  82. Nikolaus Muellner, Emmerich Seidelberger, Alessandro Del Nevo, Francesco D'Auria - Austria
    Application of the Fast Fourier Transform Based Method to Assist in the Qualification Process for the PSB-VVER1000 RELAP5 Nodalisation

     

  83. Nikolaus Muellner, Wolfgang Kromp, Gianni Petrangeli, Francesco D'Auria - Austria
    RELAP5 Analysis of an AMP Based on Non-Conventional Sources of Feed Water for a Generic VVER-1000 NPP in Case of a Total Loss of Feed Water

     

  84. Fernando Roumiguičre - Germany
    Field Experience on Zn Injection on PWR Plants for Dose Rate Reduction

     

  85. R.I. Facer - Austria
    Nuclear Energy for the 21st Century

     

  86. Vaidas Matuzas, Juozas Augutis, Vytis Kopustinskas - Lithuania
    Optimal Hydro Profiling of RBMK-1500 Reactor at Ignalina NPP in Lithuania

     

  87. Franco Pierro, Fabio Moretti, Davide Mazzini, Francesco D'Auria - Italy
    Analysis of Fuel Pin Mechanics in Case of Flow Blockage of a Single RBMK Channel

     

  88. Teodor Chirica, Alexandru Havriş - Romania
    Romanian Nuclear Power Program Development - Commitment and Challenges Ahead

     

  89. Heikki Purhonen, Markku Puustinen, Jani Laine, Antti Räsänen, Riita Kyrki-Rajamäki, Juhani Vihavainen - Finland
    Steam Blowdown Experiments with the Condensation Pool Test Rig

     

  90. Katia Slavcheva, M. Mori, Calogero Sollima - Italy
    Safety Culture and Organizational Issues During Transition from Operation to Decommissioning of NPPs

     

  91. Igor Simonovski, Leon Cizelj - Slovenia
    Correlation Length Estimation in a Polycrystalline Material Model

     



  92. Thomas Stäbler, Leonhard Meyer, Thomas Schulenberg, Eckart Laurien - Germany
    Investigations on Flow Reversal in Stratified Horizontal Flow

     

  93. Ina Yankova, Bojana Tabakova, Peter Petrov - Bulgaria
    Electron Beam Welding Reconstitution Technology of Charpy-V Specimens

     

  94. Istvan Panka, András Keresztúri, Csaba Hegedus - Hungary
    New Sparse Matrix Solver in the KIKO3D 3-Dimensional Reactor Dynamics Code

     

  95. Zoran Stošić - Germany
    On the Frontier of Boiling Curve and Beyond Design of its Origin

     

  96. Nikolay Kolev, Nikolay Petrov, Sylvie Aniel, Eric Royer, Ulrich Bieder - France
    VVER-1000 Coolant Transient (V1000CT) Benchmark - Overview and Status of Phase 2

     

  97. Isabelle Tkatschenko, Etienne Studer, Henri Paillere - France
    MISTRA Facility for Containment Lumped Parameters and CFD Codes Validation: Example of the International Standard Problem ISP47

     

  98. Gábor Házi, Gusztáv Mayer - Hungary
    Flow in Rod Bundles

     

  99. Leopold Vrankar, Goran Turk, Franc Runovc - Slovenia
    Modeling of Radionuclide Migration Through Porous Material with Meshless Method

     

  100. Milko Križman, Sonja Ambrož - Slovenia
    Measurements of the Sr-90 Radionuclide in Slovenian Soils Before and After Chernobyl Accident

     

  101. Helena Janžekovič, Janez Češarek - Slovenia
    Orphan Sources in Slovenia

     

  102. Milena Černilogar - Radež, Marko Giacomelli, Radomir Ilić - Slovenia
    Development of Etch Track Detector System for Low Fluxes of Thermal Neutrons

     

  103. Lilijana Mljač, Milko Križman - Slovenia
    Liquid Radioactive Discharges From a Thermal Power Plant

     

  104. Jelena Rašula, Andrej Stritar, Igor Osojnik, Darko Pungerčar - Slovenia
    Information System Design and its Implementation at the SNSA

     



  105. Mitja Uršič, Andrej Stritar, Djordje Vojnovič, Artur Mühleisen - Slovenia
    Evolution of the NPP Krško Safety Assessment Due to Seismic Hazard

     

  106. Leopold Vrankar - Slovenia
    Regulatory View of the Close-Out of the Uranium Ore Mine Žirovski Vrh

     

  107. Peter Jovanovič, Milko Križman - Slovenia
    Present Status of Radioactive Contamination of the Forest Ecosystem in Slovenia with Cs-137 Originating Mostly from the Chernobyl Accident

     

  108. Andrej Stritar, Dragan Mitić - Slovenia
    ROKO-Database of the Environmental Radioactivity Measurements in Slovenia

     

  109. Igor Lengar, Tomaž Žagar, Matjaž Ravnik - Slovenia
    Comparison of Activation in Fission and Fusion Spectrum Neutron Beams

     

  110. Petra Rogan, Igor Lengar, Matjaž Ravnik - Slovenia
    Evaluation of Zero Power Experiments with Second Core of FDR (Advanced Pressurized Light Water Reactor) for the Nuclear Research Ship "Otto Hahn".

     

  111. M.D. Carelli, Bojan Petrović, Nikola Čavlina, Davor Grgić - USA
    IRIS (International Reactor Innovative and Secure) - Design Overview and Deployment Prospects

     

  112. Mohamed Belgaid, A. Tassadit, F. Kadem, A. Amokrane - Algeria
    Semi-Empirical Systematics of (n,p) Reaction Cross Sections at 14.5 MeV Neutron Energy

     

  113. Abbas Ghasemizad, S. Khoshbinfar - Iran
    The Method of Self-Similar Solution for Energy Gain Scaling in ICF Targets

     

  114. Bruno Tourniaire, Bertrand Spindler - France
    Simulation of Molten Core Concrete Interaction in Oxide/Metal Stratified Configuration with the TOLBIAC-ICB Code

     

  115. Janez Perko, Božidar Šarler - Slovenia
    A Meshless Approach to Radionuclide Transport Calculations

     

  116. Wolfgang Hering, Christoph Homann - Germany
    Degraded Core Reflood: Present Knowledge Based on Experimental and Analytical Data

     

  117. Tea Bilić-Zabric, Ivica Bašić - Slovenia
    Potential Need for Re-Definition of the Highest Priority Recovery Action in the Krško SAG-1

     

  118. Jiří Křepel, Ulrich Rohde, Ulrich Grundmann - Germany
    Simulation of Molten Salt Reactor Dynamics

     

  119. Boštjan Končar, Eckhard Krepper, Yury Egorov - Slovenia
    CFD Modelling of Subcooled Flow Boiling for Nuclear Engineering Applications

     

  120. Luka Snoj, Matjaž Ravnik - Slovenia
    Effect of Fuel Particles' Size Variations on Multiplication Factor in Pebble-Bed Nuclear Reactor

     

  121. Nadja Železnik, Metka Kralj, Marko Polič, Drago Kos, Darinka Pek Drapal - Slovenia
    Assessment of Public Acceptability in Site Selection Process: The Methodology and the Results

     

  122. Antonio Expósito, César Queral, Isaac González, Juan Antonio Quiroga, Aitor Ibarra, Javier Hortal, John-Einar Hulsund, Rossella Bisio, Svein Nilsen - Spain
    Application of a Methodology for Evaluating Human Factors on Accident Sequences

     

  123. Marjan Kromar, Bojan Kurinčič - Slovenia
    Impact of the Hypothetical RCCA Rodlet Separation on the Nuclear Parameters of the NPP Krško Core

     

  124. Peter De Regge - Belgium
    The European Nuclear Education Network Association - ENEN

     

  125. Alenka Vesel, Miran Mozetič - Slovenia
    Heterogeneous Recombination of Neutral Hydrogen Atoms on Surfaces of the Fusion Relevant Materials

     

  126. Miran Mozetič, Alenka Vesel - Slovenia
    Density of Neutral Hydrogen Atoms in a Microwave Hydrogen Plasma Reactor

     

  127. Tomaž Gyergyek, Milan Čerček - Slovenia
    Multiple Solutions for the Sheath Potential Drop in Front of a Floating Electron Emitting Collector Immersed in a Two-Electron Temperature Plasma

     

  128. Vladimir Stevanovic, Zoran Stošić, Uwe Stoll - Serbia and Montenegro
    CMFD Simulations of Vertical and Horizontal Steam Generators Thermal-Hydraulics

     

  129. Marko Čepin - Slovenia
    Method for Assessing Reliability of a Network Considering Probabilistic Safety Assessment

     

  130. Primož Pelicon, Iztok Čadež, Sabina Markelj, Jure Simčič, Zdravko Rupnik - Slovenia
    Analysis of Materials Used for Plasma-Facing Components in Tokamaks with Ion Beam Analytical Techniques

     

  131. Nadja Železnik, Miran Veselič, Irena Mele, Metka Kralj - Slovenia
    Development of Site Selection Process for LILW Repository in Slovenia

     



  132. Mladen Stanojević, Jože Duhovnik, Nikola Jelić, Siegbert Kuhn - Slovenia
    Boundary Conditions for the Ion Component Fluid Velocities at the Magnetic Presheath Entrance in Multi-Component Plasmas with E×B and Diamagnetic Drifts

     

  133. Andrej Trkov, Matjaž Božič - Austria
    Simulation of an End-of-Cycle Trip Transient with the LOADF Code Package

     

  134. Anis Bousbia Salah - Italy
    Analysis of Loss of Passive Decay Heat Removal Accident in an MTR Pool Type Research Reactor

     

  135. Vesselina Ranguelova, Patricia Pla, Claude Ives Rieg, Michel Bieth - Netherlands
    JRC/IE Support Activities to PHARE Nuclear Safety Programmes: Dissemination of PHARE Project Results

     

  136. Arcadii Kisselev, Gennadii Kobelev, Valerii Strizhov, Alexander Vasiliev - Russia
    Results of Numerical Module Development for Debris Behavior in VVER Under Severe Accident Conditions

     

  137. Giacomino Bandini, Paride Meloni, Massimiliano Polidori - Italy
    Interpretation of TRIGA Reactor Experimental Data with SIMMER-III Code for RELAP5 Model Evaluation and Transient Analysis

     

  138. Siniša Šadek, Srđan Špalj, Nikola Čavlina - Croatia
    RCP Seal Leakage Analysis During Station Blackout for NPP Krško

     

  139. Maddalena Casamirra, Francesco Castiglia, Mariarosa Giardina, Paride Meloni - Italy
    RELAP5 Modification for CHEOPE Simulations

     

  140. V. Amato, Francesco Castiglia, Mariarosa Giardina - Italy
    Safety Analysis of the Containment for an ADS Demonstration Facility

     

  141. Ana Maria Sánchez Hernandez, Angelo Lo Nigro, Antonino Spadoni, Francesco D'Auria - Spain
    3D Neutronic/Thermalhydraulic Core Model with Boron Feedback

     

  142. Ivan Kodeli - France
    Analysis of the HCPB Breeder Blanket Mock-up Experiment for ITER Using SUSD3D Code

     

  143. Saša Novak, Goran Dražić, Katja Mejak, T. Toplišek - Slovenia
    Ceramic Routes for Fabrication of SiCf/SiC Composites

     

  144. Daniela Mladin - Romania
    Analysis of Area Events as Part of Probabilistic Safety Assessment for Romanian TRIGA SSR 14 MW Reactor

     

  145. Irena Mele, Borut Mavko, Igor Jenčič - Slovenia
    Educational and Training Needs in Radioactive Waste Management

     



  146. Mario Keco, Nenad Debrecin, Davor Grgić - Croatia
    Applicability of Coupled Code RELAP5/GOTHIC to NPP Krško MSLB Calculation

     

  147. Kazuhisa Yuki, Sayed Mohamad Hosseini, Y. Sugawara, H. Hashizume, M. Tanaka - Japan
    Influence of Secondary Flow on the Thermal Hydraulic Characteristics in a Mixing Tee with a 90-Degree Bend Upstream

     

  148. Anis Bousbia Salah, Tewfik Hamidouche, Hakim El-Hadjen, Mohamed Balistrou - Algeria
    Analysis of the Onset of Flow Instability in Rectangular Heated Channel Using Drift Flux Model Approach

     

  149. Christian Kirchsteiger, Ricardo Bolado, Hartmut Wider - Netherlands
    Comparison of Advanced Mid-Sized Reactors Regarding Core Damage Frequencies and Core Melt Retention Features

     

  150. Paolo Oresta, R. Verzicco, A. Soldati - Italy
    Direct Numerical Simulation of Particle Dispersion in Rayleigh-Bénard Turbulent Flows

     

  151. Thomas Schwarz, R. Bouecke, S. Odar - Germany
    Cleanliness Criteria to Improve Steam Generator Performance

     

  152. Isaac González, César Queral, Antonio Expósito, Marta Novales, Alberto Concejal, Juan Carlos Martínez-Murillo - Spain
    TRACE Model of Almaraz Nuclear Power Plant

     

  153. Damijan Miljavec, Bogomir Zidarič, Tomaž Gyergyek - Slovenia
    3-D Magnetic Field Calculation in Aerial Toroidal Coil System Arrangement

     

  154. Dušan Čalić - Slovenia
    Waste management in future Partitioning and transmutation (P&T)

     

  155. Goran Dražić, Saša Novak, Tomaž Žagar, Matjaž Ravnik - Slovenia
    Measurements of Long-lived Activation Components in the SiCf/SiC Composites

     

  156. Juraj jr. Breza, Vladimír Nečas, Petr Dařílek - Slovak Republic
    Simulation of the neutron-physical properties of the classical UO2 fuel and of MOX fuel during the burn-up by TRANSURANUS

     

  157. Kune Y. Suh, Seung Dong Lee, Sang Woo Noh - Korea, Republic
    Digital Engineering for Next Generation Nuclear Energy Systems

     

  158. Kune Y. Suh, Chan Soo Kim, Seung Dong Lee, Sang Woo Noh, - Korea, Republic
    Dual Retention Strategy for Advanced Power Reactor 1400 Mwe

     

  159. Zoran Stošić, Klaus Kuehnel, Klaus Richter - Germany
    PWR Pump Shaft Transient Analysis with COBRA 3-CP Improved by Advanced Boiling Curve Approach

     

Last update: 30/09/05

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