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.
- Damir Mandić - Slovenia
Some
Aspects of Digital I&C and Digital Human-System
Interface Upgrades in Nuclear Power Plants
- Luka Štrubelj, Iztok Tiselj - Slovenia
CFD
Simulation of Kelvin-Helmholtz Instability
-
- Dean Korošak, Bruno Cvikl, Janja Kramer, Renata
Jecl, Anita Praprotnik, Miran Veselič - Slovenia
Applications
of Fractional Calculus to Diffusion Transport in
Clay-Water System
- 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
- Sabina Markelj, Zdravko Rupnik, Iztok Čadež -
Slovenia
Detection
System for Vibrational Spectroscopy of Hydrogen
Molecules for Studies of Collision Processes in Fusion
Edge Plasma
- Ivan Vrbanić, Johan Sörman - Croatia
Framework
for Ensuring Appropriate Maintenance of Baseline PSA and
Risk Monitor Models in a Nuclear Power Plant
- Ivica Bašić, Davor Grgić - Croatia
3D
Simulation of a High Pressure Water Injection Into a
Circular Cold Leg Pipe Flow
- Miroslav Babić, Ivo Kljenak, Borut Mavko -
Slovenia
Simulation
of Atmosphere Mixing and Stratification in the ThAI
Experimental Facility with a CFD Code
- Andrej Prošek, Iztok Parzer - Slovenia
Accuracy
Quantification of RELAP5 Predictions of NPP Events
- Tomaž Žagar, Joseph Magill - Slovenia
Is
Transmutation in an "Active" Repository
Feasible?
- Matjaž Leskovar, Boštjan Končar, Leon Cizelj -
Slovenia
Simulation
of Ex-Vessel Steam Explosion in PWR Reactor Cavity
- Andrej Prošek, Matjaž Leskovar - Slovenia
Application
of FFTBM to Severe Accidents
- Iztok Parzer, Ivo Kljenak - Slovenia
ATWS
Thermal-Hydraulic Analysis for Krško Full Scope
Simulator Validation
- Andrej Prošek, Iztok Parzer - Slovenia
SB LOCA
Thermal-Hydraulic Analyses for Krško Full Scope
Simulator Validation
- Iztok Parzer, Andrej Prošek - Slovenia
Loss of
Normal Feedwater Analyses for Krško Full Scope
Simulator Validation
- Iztok Parzer, Boštjan Končar - Slovenia
SGTR
Analysis for Krško Full Scope Simulator Validation
- Robert Bergant, Iztok Tiselj - Slovenia
Numerical
Simulations of Turbulent Heat Transfer in a Channel at
Prandtl Numbers Higher than 100
- Janez Gale, Iztok Tiselj - Slovenia
Applicability
of the Godunov's Method for Fundamental Four-Equations
FSI Model
- Radko Istenič, Igor Jenčič - Slovenia
Public
Opinion About Nuclear Energy - Year 2005 Poll
-
-
- Ilija Plećaš - Serbia and Montenegro
Leaching
Study in Process of Solidification of Radionuclide 60CO
in Concrete
- Lyubomir Pironkov, Slavka Tzanova - Bulgaria
A
European Project on Development of Training Courses for
Personnel Involved in Decommissioning of Nuclear
Installations
- Nikita Hristov, Valentin Papazov - Bulgaria
Application
of PSA Results for Prioritisation of Cable Penetrations
Reinforcement from Seismic Point of View
-
- Nathalie Dessars - Belgium
Extension
of Severe Accident Management Guidelines to Shutdown and
Low-Power Operation Modes Based on the WOG SAMG Approach
- 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.
- 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
-
- John Emmett, Bob Smith - United Kingdom
The Use
of Modern Software Based Instrumentation in Safety
Critical Applications
- Lidia Kinova, T. Grigorov, P. Nikolov, P. Petrova -
Bulgaria
Initial
Radiological Activity Waste Categorization for Partial
Dismantling of Research Reactor IRT- 2000, Sofia
- 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
- 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
-
- Danut Bujoreanu, I.V. Popescu - Romania
Measurement
of the Leachability of Solidified Low - Level
Radioactive Wastes Contaminated with C-14 Resulted from
Cernavoda NPP
- 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
- Norbert Jakobs, Rudolf Baumgartl - Germany
Visual
Inspection, Better Than Your Eyes
- Dino Araneo, Alessandro Del Nevo, Francesco D'Auria,
Giorgio Maria Galassi - Italy
Scaling
of Small Break LOCA in VVER 1000 System
- Patrice Giordano, Luis E. Herranz, Tim Haste,
Jean-Claude Micaelli - France
SARNET:
Severe Accident Research Network Key Issues in the Area
of Source Term
- Martin Kropík, Monika Juŕičková, Karel Matějka
- Czech Republic
New
Digital Control and Power Protection System of VR 1
Training Reactor
-
- Norbert Jakobs, Rudolf Baumgartl - Germany
Appearances
can be Deceptive, Innovative Laser Profilometry Enhances
Your Safety
- 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
-
-
- 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
- Mirela Nitoi, Margarit Pavelescu, Ilie Turcu,
Gheorghe Florescu, Minodora Apostol, Mita Farcasiu -
Romania
Ageing
Effects Modelling in Probabilistic Safety Assessment of
Nuclear Power Plants
- 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
- V. Balaceanu, Viorel Hristea - Romania
Study
of the End Flux Peaking for the CANDU Fuel Bundle Types
by Transport Methods
-
- Lubor Žežula - Czech Republic
Method
of Public Support Evaluation for Advanced NPP Deployment
- 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
- Algirdas Kaliatka, Mindaugas Vaisnoras - Lithuania
Simulation
of Water Hammer Experiments Using RELAP5 Code
-
- 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
- Gabriel Farkas, Vladimír Slugeň, Peter Domonkoš
- Slovak Republic
Nuclear
Analysis of the EUROFER 97 Alloy by MCNP-4C2 Code
- Vladimír Slugeň, Vladimir Krsjak - Slovak
Republic
Non-Destructive
Evaluation of WWER-Class RPV Steels
- Ján Mikuš - Czech Republic
Fuel
Pin Bowing and Related Investigation of WWER-440 Control
Rod Influence on Power Release Inside of Neighbouring
Fuel Pins
-
- 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
- Evgeny Kapralov - Russia
Refresher
Training as an Important Factor Affecting Safety of
Atomic Energy Utilization Facilities
- 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
- Mihai Culcer, Mariana Iliescu, Marian Curuia,
Adrian Enache, Mircea Raceanu, Ioan Stefanescu, Catalin
Ducu, Viorel Malinovschi - Romania
Automatic
System for Tritium Contaminated Surface Monitoring
- 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
- Sofia Carlos, Enrico Zio - Spain
Detection
of Malfunctions in the Secondary System of a Nuclear
Power Plant by Neural Networks
- Thomas Frank, Philip Zwart, Junmei Shi, Eckhard
Krepper, Dirk Lucas, Ulrich Rohde - Germany
Inhomogeneous
MUSIG Model - A Population Balance Approach for
Polydispersed Bubbly Flows
-
- Monsefi Mehrdad, Nilforooshan Behnam, Hojabri
Alireza, Nima Vaziri - Iran
Study
of Chemical Precipitation of Cs
- Tino Liebschner, Burkhard Heidowitzsch - Germany
Advanced
Digital I&C Technology in Nuclear Power Plants - A
Success Story from Finland and China
-
- 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
- Tewfik Hamidouche, Anis Bousbia Salah, Martina
Adorni, Francesco D'Auria - Italy
Analysis
of Loss of Coolant Accident in MTR Pool Type Research
Reactors
- 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
- Hans Helmut Over, Erik Wolfart, Claude Ives Rieg -
Netherlands
The
Material and Document Management Databases of JRC Petten
- Useful Tools for European Nuclear Society
- 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
- Juozas Augutis, Inga Zutautaite - Lithuania
Estimation
of Parameters in Ageing Model Using Bayesian Approach
- Johan Sörman - Sweden
Evaluation
of Test Intervals Strategies with the Use of Risk
Monitor
- 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
- 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
- George Bereznai, William Garland - Canada
The
Role of Universities in Managing Canada's Nuclear
Knowledge
- Gheorghe Negut, Ilie Prisecaru - Romania
RIA
Type Tests Model Modeled with RELAP5-SCDAP
-
- J. Zmitkova, C.M. Allison, J.K. Hohorst - Czech
Republic
Application
of RELAP/SCDAPSIM/MOD3.4 for Czech Republic Research
Reactor Applications
-
-
- Reza Jafarian, Kamran Sepanloo - Iran
Human
Reliability Analysis for Steam Generator Feed-and-Bleed
Accident in Bushehr NPP-1
- Claire Blackett, Joe Carthy, Anne Drummond, John
Dunnion - Ireland
Combining
Accident Analysis Methods for Organisational Safety
- 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
-
- 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
- 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
- György Hegyi, Gábor Hordósy - Hungary
The
Results of Comparison of Benchmark Calculations for
Hexagonal Lattices with Different Methods
- 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
- Radim Briš - Czech Republic
RCM
Optimization of a Distribution System under both
Preventive and Corrective Maintenance
-
- Péter Windberg, E. Perez-Feró - Hungary
Mechanical
Test of E110 Cladding Material Oxidized in Hydrogen Rich
Steam Atmosphere
- Eckhard Krepper, Alexander Grahn - Germany
Numerical
Investigations for Insulation Particle Transport
Phenomena in Water Flow
- 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
-
- 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
- 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
- Fernando Roumiguičre - Germany
Field
Experience on Zn Injection on PWR Plants for Dose Rate
Reduction
- R.I. Facer - Austria
Nuclear
Energy for the 21st Century
- Vaidas Matuzas, Juozas Augutis, Vytis Kopustinskas
- Lithuania
Optimal
Hydro Profiling of RBMK-1500 Reactor at Ignalina NPP in
Lithuania
- 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
- Teodor Chirica, Alexandru Havriş - Romania
Romanian
Nuclear Power Program Development - Commitment and
Challenges Ahead
- Heikki Purhonen, Markku Puustinen, Jani Laine,
Antti Räsänen, Riita Kyrki-Rajamäki, Juhani
Vihavainen - Finland
Steam
Blowdown Experiments with the Condensation Pool Test Rig
- Katia Slavcheva, M. Mori, Calogero Sollima - Italy
Safety
Culture and Organizational Issues During Transition from
Operation to Decommissioning of NPPs
- Igor Simonovski, Leon Cizelj - Slovenia
Correlation
Length Estimation in a Polycrystalline Material Model
-
- Thomas Stäbler, Leonhard Meyer, Thomas Schulenberg,
Eckart Laurien - Germany
Investigations
on Flow Reversal in Stratified Horizontal Flow
- Ina Yankova, Bojana Tabakova, Peter Petrov -
Bulgaria
Electron
Beam Welding Reconstitution Technology of Charpy-V
Specimens
- Istvan Panka, András Keresztúri, Csaba Hegedus -
Hungary
New
Sparse Matrix Solver in the KIKO3D 3-Dimensional Reactor
Dynamics Code
- Zoran Stošić - Germany
On the
Frontier of Boiling Curve and Beyond Design of its
Origin
- Nikolay Kolev, Nikolay Petrov, Sylvie Aniel, Eric
Royer, Ulrich Bieder - France
VVER-1000
Coolant Transient (V1000CT) Benchmark - Overview and
Status of Phase 2
- Isabelle Tkatschenko, Etienne Studer, Henri
Paillere - France
MISTRA
Facility for Containment Lumped Parameters and CFD Codes
Validation: Example of the International Standard
Problem ISP47
- Gábor Házi, Gusztáv Mayer - Hungary
Flow in
Rod Bundles
- Leopold Vrankar, Goran Turk, Franc Runovc -
Slovenia
Modeling
of Radionuclide Migration Through Porous Material with
Meshless Method
- Milko Križman, Sonja Ambrož - Slovenia
Measurements
of the Sr-90 Radionuclide in Slovenian Soils Before and
After Chernobyl Accident
- Helena Janžekovič, Janez Češarek - Slovenia
Orphan
Sources in Slovenia
- Milena Černilogar - Radež, Marko Giacomelli,
Radomir Ilić - Slovenia
Development
of Etch Track Detector System for Low Fluxes of Thermal
Neutrons
- Lilijana Mljač, Milko Križman - Slovenia
Liquid
Radioactive Discharges From a Thermal Power Plant
- Jelena Rašula, Andrej Stritar, Igor Osojnik, Darko
Pungerčar - Slovenia
Information
System Design and its Implementation at the SNSA
-
- Mitja Uršič, Andrej Stritar, Djordje Vojnovič,
Artur Mühleisen - Slovenia
Evolution
of the NPP Krško Safety Assessment Due to Seismic
Hazard
- Leopold Vrankar - Slovenia
Regulatory
View of the Close-Out of the Uranium Ore Mine Žirovski
Vrh
- 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
- Andrej Stritar, Dragan Mitić - Slovenia
ROKO-Database
of the Environmental Radioactivity Measurements in
Slovenia
- Igor Lengar, Tomaž Žagar, Matjaž Ravnik -
Slovenia
Comparison
of Activation in Fission and Fusion Spectrum Neutron
Beams
- 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".
- M.D. Carelli, Bojan Petrović, Nikola Čavlina,
Davor Grgić - USA
IRIS
(International Reactor Innovative and Secure) - Design
Overview and Deployment Prospects
- Mohamed Belgaid, A. Tassadit, F. Kadem, A. Amokrane
- Algeria
Semi-Empirical
Systematics of (n,p) Reaction Cross Sections at 14.5 MeV
Neutron Energy
- Abbas Ghasemizad, S. Khoshbinfar - Iran
The
Method of Self-Similar Solution for Energy Gain Scaling
in ICF Targets
- Bruno Tourniaire, Bertrand Spindler - France
Simulation
of Molten Core Concrete Interaction in Oxide/Metal
Stratified Configuration with the TOLBIAC-ICB Code
- Janez Perko, Božidar Šarler - Slovenia
A
Meshless Approach to Radionuclide Transport Calculations
- Wolfgang Hering, Christoph Homann - Germany
Degraded
Core Reflood: Present Knowledge Based on Experimental
and Analytical Data
- Tea Bilić-Zabric, Ivica Bašić - Slovenia
Potential
Need for Re-Definition of the Highest Priority Recovery
Action in the Krško SAG-1
- Jiří Křepel, Ulrich Rohde, Ulrich Grundmann -
Germany
Simulation
of Molten Salt Reactor Dynamics
- Boštjan Končar, Eckhard Krepper, Yury Egorov -
Slovenia
CFD
Modelling of Subcooled Flow Boiling for Nuclear
Engineering Applications
- Luka Snoj, Matjaž Ravnik - Slovenia
Effect
of Fuel Particles' Size Variations on Multiplication
Factor in Pebble-Bed Nuclear Reactor
- 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
- 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
- Marjan Kromar, Bojan Kurinčič - Slovenia
Impact
of the Hypothetical RCCA Rodlet Separation on the
Nuclear Parameters of the NPP Krško Core
- Peter De Regge - Belgium
The
European Nuclear Education Network Association - ENEN
- Alenka Vesel, Miran Mozetič - Slovenia
Heterogeneous
Recombination of Neutral Hydrogen Atoms on Surfaces of
the Fusion Relevant Materials
- Miran Mozetič, Alenka Vesel - Slovenia
Density
of Neutral Hydrogen Atoms in a Microwave Hydrogen Plasma
Reactor
- 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
- Vladimir Stevanovic, Zoran Stošić, Uwe Stoll -
Serbia and Montenegro
CMFD
Simulations of Vertical and Horizontal Steam Generators
Thermal-Hydraulics
- Marko Čepin - Slovenia
Method
for Assessing Reliability of a Network Considering
Probabilistic Safety Assessment
- 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
- Nadja Železnik, Miran Veselič, Irena Mele, Metka
Kralj - Slovenia
Development
of Site Selection Process for LILW Repository in
Slovenia
-
- 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
- Andrej Trkov, Matjaž Božič - Austria
Simulation
of an End-of-Cycle Trip Transient with the LOADF Code
Package
- Anis Bousbia Salah - Italy
Analysis
of Loss of Passive Decay Heat Removal Accident in an MTR
Pool Type Research Reactor
- Vesselina Ranguelova, Patricia Pla, Claude Ives
Rieg, Michel Bieth - Netherlands
JRC/IE
Support Activities to PHARE Nuclear Safety Programmes:
Dissemination of PHARE Project Results
- Arcadii Kisselev, Gennadii Kobelev, Valerii
Strizhov, Alexander Vasiliev - Russia
Results
of Numerical Module Development for Debris Behavior in
VVER Under Severe Accident Conditions
- Giacomino Bandini, Paride Meloni, Massimiliano
Polidori - Italy
Interpretation
of TRIGA Reactor Experimental Data with SIMMER-III Code
for RELAP5 Model Evaluation and Transient Analysis
- Siniša Šadek, Srđan Špalj, Nikola Čavlina -
Croatia
RCP
Seal Leakage Analysis During Station Blackout for NPP Krško
- Maddalena Casamirra, Francesco Castiglia, Mariarosa
Giardina, Paride Meloni - Italy
RELAP5
Modification for CHEOPE Simulations
- V. Amato, Francesco Castiglia, Mariarosa Giardina -
Italy
Safety
Analysis of the Containment for an ADS Demonstration
Facility
- Ana Maria Sánchez Hernandez, Angelo Lo Nigro,
Antonino Spadoni, Francesco D'Auria - Spain
3D
Neutronic/Thermalhydraulic Core Model with Boron
Feedback
- Ivan Kodeli - France
Analysis
of the HCPB Breeder Blanket Mock-up Experiment for ITER
Using SUSD3D Code
- Saša Novak, Goran Dražić, Katja Mejak, T. Toplišek
- Slovenia
Ceramic
Routes for Fabrication of SiCf/SiC Composites
- Daniela Mladin - Romania
Analysis
of Area Events as Part of Probabilistic Safety
Assessment for Romanian TRIGA SSR 14 MW Reactor
- Irena Mele, Borut Mavko, Igor Jenčič - Slovenia
Educational
and Training Needs in Radioactive Waste Management
-
- Mario Keco, Nenad Debrecin, Davor Grgić - Croatia
Applicability
of Coupled Code RELAP5/GOTHIC to NPP Krško MSLB
Calculation
- 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
- 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
- Christian Kirchsteiger, Ricardo Bolado, Hartmut
Wider - Netherlands
Comparison
of Advanced Mid-Sized Reactors Regarding Core Damage
Frequencies and Core Melt Retention Features
- Paolo Oresta, R. Verzicco, A. Soldati - Italy
Direct
Numerical Simulation of Particle Dispersion in Rayleigh-Bénard
Turbulent Flows
- Thomas Schwarz, R. Bouecke, S. Odar - Germany
Cleanliness
Criteria to Improve Steam Generator Performance
- Isaac González, César Queral, Antonio Expósito,
Marta Novales, Alberto Concejal, Juan Carlos Martínez-Murillo
- Spain
TRACE
Model of Almaraz Nuclear Power Plant
- Damijan Miljavec, Bogomir Zidarič, Tomaž Gyergyek
- Slovenia
3-D
Magnetic Field Calculation in Aerial Toroidal Coil
System Arrangement
- Dušan Čalić - Slovenia
Waste
management in future Partitioning and transmutation
(P&T)
- Goran Dražić, Saša Novak, Tomaž Žagar, Matjaž
Ravnik - Slovenia
Measurements
of Long-lived Activation Components in the SiCf/SiC
Composites
- 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
- Kune Y. Suh, Seung Dong Lee, Sang Woo Noh - Korea,
Republic
Digital
Engineering for Next Generation Nuclear Energy Systems
- Kune Y. Suh, Chan Soo Kim, Seung Dong Lee, Sang Woo
Noh, - Korea, Republic
Dual
Retention Strategy for Advanced Power Reactor 1400 Mwe
- Zoran Stošić, Klaus Kuehnel, Klaus Richter -
Germany
PWR
Pump Shaft Transient Analysis with COBRA 3-CP Improved
by Advanced Boiling Curve Approach
-
|
|