1. No category

Program
Conference Timetable
All lectures and posters session will be held in Grand Hotel Bernardin at Europa Convention Halls
“A” and “C“.
Monday, Sept. 8
Tuesday, Sept. 9
Wednesday, Sept. 10
Invited lecture
Christophe Behar
8:30 - 9:10
400
Multiphysics
9:10 - 9:50
500
Probabilistic safety
assessment
9:50 - 10:30
Coffee break
900
Thermal-hydraulics I
8:30 - 9:30
Coffee break
900
Thermal-hydraulics II
9:50 - 10:50
Thursday, Sept. 11
Invited lecture
Francesco Romanelli
8:30 - 9:10
1100
Nuclear fusion
9:10 - 10:30
Coffee break
Coffee break
600
Reactor physics
10:50 - 12:30
Lunch
Conference opening
14:00
Invited lecture
Rauno Rintamaa
14:20 - 15:00
200
Nuclear energy & society
15:00 - 16:00
Lunch
1200
Materials, integrity
and life management
10:50 - 12:30
Lunch
700
Research reactors
14:00 - 15:00
Posters with Coffee break
15:00 - 16:40
Coffee break
300
Severe accidents
16:20 - 18:00
1000
Nuclear power plant
operation
11:10 - 12:30
Conference trip
14:00 - 18:00
800
Radioactive waste &
decommissioning
16:40 - 18:00
Welcome reception
19:00 23rd International Conference Nuclear Energy for New Europe Conference dinner
19:00 i
Program
Conference Program
as per September 5, 2014
Monday, September 8
14:00
Conference Opening
Invited lecture
14:20 102 Rauno Rintamaa - Finland
Finnish approach for synergistic effects of research, reliability and safety in nuclear
energy
Session 1
15:00
Nuclear energy & society
Chairpersons:
Igor Jenčič, Slovenia
Michel Giot, Belgium
15:00 201
Helena Janžekovič - Slovenia
Nuclear Industry and European BSS
15:20 208
Radko Istenič, Igor Jenčič - Slovenia
Public Opinion about Nuclear Energy – Year 2014 Poll
15:40 203
Luka Snoj, Sebastjan Rupnik, Anže Jazbec - Slovenia
New Training Experiments at the JSI TRIGA Mark II Reactor
Session 2
16:20
Severe accidents
Chairpersons:
Ivo Kljenak, Slovenia
Gerard Cognet, France
16:20 301
Tim Haste, Mirco Di Giuli, Gunter Weber, Sebastian Weber - France
Iodine Benchmarks in the SARNET2 Network of Excellence
16:40 302
Alexander D. Vasiliev, Juri Stuckert - Russian Federation
Application of Thermal Hydraulic and Severe Accident Code SOCRAT/V3 to Bottom
Water Reflood Experiment QUENCH-LOCA-1
17:00 303
Matjaž Leskovar, Vasilij Centrih - Slovenia
Influence of Zirconium Oxidation on Steam Explosion Energetics
17:20 306
Davor Grgić, Tomislav Fancev, Siniša Šadek, Vesna Benčik - Croatia
Spatial Distribution of Hydrogen in NEK Containment
17:40 305
Alain Flore Y Flores, Vaidas Matuzas, Luca Ammirabile - Netherlands
Analysis of CABRI-BI1 loss-of-flow experiment using ASTEC-Na
ii23rd International Conference Nuclear Energy for New Europe
Program
Tuesday, September 9
8:30
Invited lecture
101
Session 3
Christophe Behar - France
Nuclear energy, an energy for the future
9:10Multiphysics
Chairpersons:
Miroslav Gregorič, Slovenia
Davor Grgić, Croatia
9:10
401
Agustin Abarca, Rafael Miró, Gumersindo Verdú - Spain
Analysis of Thermalhydraulic Fluctuations in Trillo NPP with
CTF/PARCSv2.7 Coupled Code
9:30
402
Bing Xia, Fu Li, Chunlin Wei, Fubing Chen - China
Neutronics and Thermal-hydraulics Study on Maximizing In Situ Utilization of
U-233 in the Th-U5-fueled HTR-PM
Session 4
9:50
Probabilistic safety assessment
Chairpersons:
Miroslav Gregorič, Slovenia
Davor Grgić, Croatia
9:50
501
Jan Prochaska - Slovakia
Evaluation of dependency of human errors in PSA
10:10 502
Peter Schimann - Germany
Benefits Of Robustness Analysis - Robustness Case Studies in European NPP´s
Session 5
10:50
Reactor physics
Chairpersons:
Ivan Aleksander Kodeli, Slovenia
Dubravko Pevec, Croatia
10:50 601 Stefan Cerba, Branislav Vrban, Jakub Lüley, Vladimir Nečas - Slovakia
Evaluation of the efectiveness of a simple GFR2400 heterogenous control rod
design
11:10 602
Branislav Vrban, Gabriel Farkas, Ján Haščík, Jakub Lüley, Stefan Cerba,
Vladimir Nečas, Peter Urban - Slovakia
Verification of Power Distribution of real fuel loadings in WWER-440 reactor
11:30 603
Fausto Franceschini, Marjan Kromar, Dušan Ćalić, Andrew Godfrey, Jess Gehin - USA
Simulation of the NPP Krško startup core with CASL core simulator, VERA-CS
11:50 606
Dušan Ćalić, Marjan Kromar - Slovenia
Determination and validation of fuel cooling with the use of isotopic factors
12:10 605
Nefeli Chrysanthopoulou, Gregory-Kyriakos Delipei, Panayiota Savva,
Melpomeni Varvayanni, Nicolas Catsaros - Greece
Computational study of neutron screens performance considering different
absorbing materials
23rd International Conference Nuclear Energy for New Europe iii
Program
Session 6
14:00
Research reactors
Chairpersons:
Luka Snoj, Slovenia
Helmuth Böck, Austria
14:00 701
Mehmet Türkmen, Üner Çolak - Turkey
Fuel Burnup Calculation in ITU TRIGA Mark II Research Reactor by Using Monte
Carlo Method
14:20 702
Marcella Cagnazzo, Christina Raith, Mario Villa, Helmuth Böck - Austria
Measurements of the in-core neutron flux distribution and energy spectrum
at the TRIGA Mark II reactor of the Vienna University of Technology/Atominstitut
14:40 703
Žiga Štancar, Luka Snoj - Slovenia
Thermal power calibration of the TRIGA Mark II reactor
Session 715:00 ‒ 16:40
Poster session
Chairpersons:
Gerard Cognet, France
Helmuth Böck, Austria
Igor Lengar, Slovenia
Nuclear energy and society
204
Melita Lenošek Kavčič, Mojca Drevenšek - Slovenia
Improving nuclear literacy through e-communication: the “eWorld” web project
205
Drago Kos, Marko Polič, Nadja Železnik - Slovenia
Nuclear Communication Divide
206
Tomaž Skobe - Slovenia
Travelling Exhibition Fusion Expo
207
Žiga Arnšek, Tomaž Ploj, Jože Špiler - Slovenia
Nuclear Power Plant Krško 2 Action Plan
209
Rolando Calabrese - Italy
Public opinion and nuclear energy: INPRO methodology and recent findings
in the open literature
210
Anna Kazakova, Yury Kapralov, Elena Kosheleva, Anna Ionova - Russian Federation
Experience of Foreign Specialists Training Based on Training Programs for
Inspection Personnel of Regulatory Body
211
Tomaž Nemec - Slovenia
Regulatory oversight of activities following the discovery of damaged fuel
assemblies during the Krško NPP outage 2013
212
Andrej Stritar, Barbara Vokal Nemec, Michel Cindro - Slovenia
Sensitivity analyses to support determination of emergency planning zones
around the nuclear power plant
213
Davor Lovinčič - Slovenia
Regulatory Review of the second Periodic Safety Review of the Krško NPP
214
Matjaž Koželj - Slovenia
ALARA in Practice
iv23rd International Conference Nuclear Energy for New Europe
Program
215
Aleš Kelhar - Slovenia
Bid Technical Evaluation Process for JEK 2 Project
Severe accidents
308
Matjaž Leskovar, Vasilij Centrih - Slovenia
Analysis of Stratified Steam Explosions
309
Ivo Kljenak - Slovenia
Simulation of THAI Hydrogen Deflagration Experiments with Upward Flame
Propagation in Homogeneous Atmosphere using ASTEC Severe Accidents Code
310
Tadej Holler, Marko Matkovič, Ivo Kljenak - Slovenia
Simulation of Hydrogen Deflagration Experiment Including Initial Turbulence
Sensitivity Test with Fluent Computational Fluid Dynamics Code
311 Helena Janžekovič, Andrej Stritar, Darja Slokan Dušič, Marjan Tkavc,
Barbara Vokal Nemec - Slovenia
Development of the Post-Accident Strategy after the Nuclear or Radiological
Accident
312
Mirco Di Giuli, Tim Haste, Regis Biehler - Italy
SARNET benchmark on Phébus FPT3 integral experiment on core degradation and
fission products behaviour
313
Mirco Di Giuli, Marco Sumini - Italy
Pressurized Water Small and Medium Reactor (SMR) Modelization and Severe
Accident Analysis using ASTEC code
314
Mitja Uršič, Renaud Meignen, Gabrijela Ikovic - Slovenia
Transition boiling modelling in the MC3D code
Multiphysics
403 Antonios Mylonakis, Melpomeni Varvayanni, Dimokratis Grigoriadis,
Panayiota Savva, Nicolas Catsaros, Alexandros Clouvas - Greece
Optimization of an integrated neutronic/thermal-hydraulic reactor core analysis
model
404
405
406
György Hegyi, Andras Kereszturi, István Pataki, Ádám Tóta, Kiril Velkov,
Ihor Pasichnyk, Yann Périn - Hungary
Coupling the ATHLET3.0 and the KIKO3DMG multigroup 3D kinetic code developed
for the fast spectrum Gen4 reactors
Consuelo Gómez-Zarzuela, Teresa Barrachina, Agustin Abarca, Rafa Miró,
Gumersindo Verdú - Spain
Peach Bottom Low Flow Stability Analysis with TRACE/PARCS
Romain Henry, Iztok Tiselj - Slovenia
A new coupling CFD/Monte Carlo neutron transport scheme, Application to
a single fuel rod problem
23rd International Conference Nuclear Energy for New Europe v
Program
Probabilistic safety assessment
503
Peter Simurka - Slovakia
Overview of Fire PSA and supporting software
504
Volodymyr Skalozubov, Igor Kozlov, Victor Kolykhanov, Anton Mazurenko,
Tetyana Gerasimenko - Ukraine
Analysis of Possible Flooding of Industrial Site Zaporizhia NPP at Joint Impact of
a Beyond Design Basis Earthquake and a Tornado in a Pond Cooler
505
Blaže Gjorgiev, Andrija Volkanovski - Slovenia
PSA analyses of mitigation strategies for extreme external events
506
Marko Čepin - Slovenia
Assessment of Loss of Offsite Power Initiating Event Frequency
Reactor physics
607
Mario Matijević, Dubravko Pevec, Krešimir Trontl - Croatia
Modeling of PWR Biological Shield Boration Using SCALE6.1 Hybrid Shielding
Methodology
608
Antonia Labarile, Nicolás Olmo, Teresa Barrachina, Agustin Abarca, Rafael Miró,
Gumersindo Verdú - Spain
Uncertainty Analysis in Reactor Physics Modeling in the Framework of
UAM-Benchmark Using SERPENT and SCALE-6.2 for Transport Calculations and
TSUNAMI and SAMPLER for Cross Section Perturbation
609
Slavko Slavič, Ivan Aleksander Kodeli, Vladimir Radulović - Slovenia
Windows interface environment XSUN-2013 for NEA transport and sensitivityuncertainty computer codes TRANSX-2, PARTISN and SUSD3D
610
Tadeja Polach, Ivica Bašić, Luka Štrubelj - Slovenia
Evaluation of the Point Kinetic Model of NEK in APROS
611
Federico Rocchi, Marco Sumini, Antonio Guglielmelli - Italy
Scale 6.1 evaluation of the effective cross sections of a LWR assembly-reflector
model with application to the NEA TMI-1 PWR Benchmark
612
Marjan Kromar, Fausto Franceschini - Slovenia
Reactor Physics Analysis of the Krško NPP by JSI and Westinghouse
613
Thalia Xenofontos, Gregory-Kyriakos Delipei, Panayiota Savva,
Melpomeni Varvayanni, Jacques Mailliard, Jorge Silva, Nicolas Catsaros - Greece
Fluence Rate Benchmarking of the Stochastic Neutronic Code ANET
614 Gregory-Kyriakos Delipei, Panayiota Savva, Melpomeni Varvayanni,
Nicolas Catsaros - Greece
VENUS-2 MOX Core Benchmark Analysis using MCNP5 1.40 with JEFF 3.1.2 and
ENDF/B-VII.0 nuclear data sets
615
Alberto Milocco, Andrej Trkov, Ivan Aleksander Kodeli - Italy
A platform for the validation of nuclear data based on the ASPIS series
of experiments in the SINBAD database
vi23rd International Conference Nuclear Energy for New Europe
Program
Research reactors
704
Eleonora Klara Skrzypek, Krzysztof Gomulski, Maciej Skrzypek - Poland
MARIA Research Reactor Thermalhydraulic Calculations With RELAP5 Code.
705
Aljaž Kolšek, Luka Snoj, Patrick Sauvan - Slovenia
Calculations to support design and installation of the DT Converter in TRIGA Mark-II
706 Gašper Žerovnik, Tanja Kaiba, Anže Jazbec, Sebastjan Rupnik, Loic Barbot,
Damien Fourmentel, Luka Snoj, Jean-François Villard - Slovenia
Validation of the neutron and gamma flux distributions in the JSI TRIGA reactor
core
707
708
Aljaž Kolšek, Luka Snoj - Slovenia
Physical Analysis of Thermalization in Thermal Column Irradiation Position
709
Vid Merljak, Andrej Trkov, Igor Lengar - Slovenia
Comparison of Measured and Calculated Reactivity Worth of Control Rods in
a TRIGA Reactor
710
Vid Merljak, Andrej Trkov - Slovenia
Kinetic Simulation of Control Rod Reactivity Worth Measurement in a TRIGA
Reactor by the Rod-Drop Method
711
Dušan Ćalić - Slovenia
Analysis of neutron flux and reaction rates of TRIGA research reactor using Monte
Carlo code Serpent
Jakub Lüley, Stefan Cerba, Ján Haščík, Branislav Vrban, Vladimir Nečas,
Jan Rataj - Slovakia
Determination of Computational Bias for Sub-critical Configuration of VR-1
712 Simon Adu, Marco Lanfredini, Francesco D‘Auria - Slovenia
Application of best estimate plus uncertainty in review of research reactor safety
analysis
Radioactive waste and decommissioning
805
Amine Bouhaddane, Gabriel Farkas, Vladimír Slugeň - Slovakia
MCNP calculations in connection to the decommissioning scenario
806
Ilija Plećaš, Dalibor Arbutina - Serbia
Modeling of Physico-Chemical Characteristics of Concrete for Filling Trenches in
Radioactive Waste Management
808
Boštjan Duhovnik, Janja Špiler - Slovenia
Optimization of the Vrbina LILW Repository Preliminary Design
810
Marko Kostanjevec, Simona Sucic - Slovenia
The Solidification of Liquid Radioactive Waste – New Technique and Knowledge
Applied in Institutional Waste Management in Slovenia
23rd International Conference Nuclear Energy for New Europe vii
Program
Thermal-hydraulics
907
909
910
911
912
914
915
Ján Kubačka, Peter Juriš, Martin Gajdoš - Slovakia
Code-to-code comparison of the VVER 440/V213 containment response to
the DBA
Andrej Prošek, Marko Matkovič - Slovenia
RELAP5 analysis of Krško nuclear power plant abnormal event from 2011
Slavomir Bebjak, Tomas Kliment - Slovakia
Supporting Deterministic T-H Analyses for Level 1 PSA
Klemen Debelak, Tadeja Polach, Ivica Bašić, Luka Štrubelj - Slovenia
Steam Generator Modeling in Apros
Jure Jazbinšek, Ivica Bašić, Luka Štrubelj - Slovenia
Modeling of Low Pressure Injection System of NEK in computer code APROS
Oleksandr Lisovyy - Italy
Capability of TRANSURANUS code to reproduce LOCA integral test results
Ovidiu-Adrian Berar, Andrej Prošek, Borut Mavko - Slovenia
TRACE Three Dimensional Pressure Vessel Model Development for Krško NPP
916
Matej Tekavčič, Boštjan Končar, Ivo Kljenak - Slovenia
Simulation of flooding waves in vertical air-water churn flow using
Neptune_CFD 2.2.0 code
917
Dejan Slovenc, Samo Fürst, Ivica Bašić, Luka Štrubelj - Slovenia
Dynamic Simulation of NEK Reactor Coolant Pump with Best Estimate Full Scale
Model in APROS
918
Rolando Calabrese, Arndt Schubert, Paul Van Uffelen, Luka Vlahović,
Csaba Gyori - Italy
Upper plenum temperature calculations: comparison of TRANSURANUS with
a 2–D model under steady–state conditions
919
Sándor Kiss, Sándor Lipcsei - Hungary
Investigation of coolant temperature fluctuations circulating in the primary circuit
of VVER-440 reactors
920
Blaž Mikuž, Iztok Tiselj - Slovenia
Numerical simulations of a turbulent flow in a fuel assembly
viii23rd International Conference Nuclear Energy for New Europe
Program
Nuclear power plant operation
1001
Aleksandra Antolovič, Bruno Glaser, Ivica Bašić, Ivan Vrbanić - Slovenia
Krško NPP 2nd Periodic Safety Review Lessons Learned
1005
Milko Janez Križman, Matjaž Stepišnik - Slovenia
Historical Review of Exposure due to the C-14 Discharges from the Krško NPP
1006
Peter Schimann - Germany
Passive Heat-removal Systems
1007
Bryan Friedman, Adam Malinowski, Ernesto Boronat De Ferrater - USA-Pensylvania
Post-Fukushima Assessment of the AP1000® Plant
1008
Igor Fifnja - Slovenia
Quality Assurance Oversight of Important Plant Functional Areas
1009
Volodymyr Skalozubov, Igor Kozlov, Victor Kolykhanov, Gennadiy Oborskiy,
A.A. Hudyma - Ukraine
Evaluating the Conditions and Impact on the Reactor Vessel of Thermal Shock
1010
Marjan Kromar, Bojan Kurinčič, Urban Simončič - Slovenia
Neutron noise analysis in the NPP Krško
1011
Franc Škrabec, Frank Courtney - Slovenia
Reactor Vessel Closure Head Replacement at Krško NPP
1013
Matko Orsag, Zdenko Kovačić, Stjepan Flegarić, Kristijan Brkić,
Borislav Balac - Croatia
RJET – 111: Autonomous Mobile Robot for Water Intake Channel Maintenance in
Power Plant Cooling Systems
Nuclear fusion
1101
Alenka Vesel, Aleksander Drenik, Miran Mozetič, Marianne Balat-Pichelin,
Jan Stockel, Jozef Varju, Radomir Panek - Slovenia
Treatment of Inconel alloy from COMPASS tokamak with O2 and H2 plasma at high
temperature
1102
Ivan Aleksander Kodeli, Vladimir Radulović, Darko Kavšek, Władysław Pohorecki,
Tadeusz Kuc - Slovenia
TRIGA Irradiations of Mn foils and TLD as Potential Tritium Production Monitors
for Fusion Applications
1105 Nikola Jelić, Leon Kos - Austria
Towards a theory of collisionless-discharges with imbalanced global
charge-outfluxes
1106
Tomaž Gyergyek, Jernej Kovačič - Slovenia
On the Role of the Source Term in a Fluid Model of the Sheath Formation in
an Oblique Magnetic Field
1107
Lojze Gačnik, Jernej Kovačič, Tomaž Gyergyek - Slovenia
PIC Simulations of an Ion Energy Analyzer
23rd International Conference Nuclear Energy for New Europe ix
Program
1109
Leon Kos - Slovenia
Visualization schema for fusion data structures
1110
Anže Založnik, Sabina Markelj, Iztok Čadež, Primož Pelicon, Porosnicu Corneliu,
Cristian P. Lungu - Slovenia
The influence of nitrogen co-deposition in mixed layers on deuterium retention
and thermal desorption
1111
Saša Novak, Aljaž Ivekovič - Slovenia
Fabrication and characterization of W-based composites
Materials, integrity and life management
1208
Oriol Costa Garrido, Samir El Shawish, Leon Cizelj - Slovenia
Uncertainties in Fatigue Life Assessment of Pipes due to Random Thermal Loads
1209
Marta Cerini, Giuseppe Dia, Elena Macerata, Eros Mossini, Marco Giola,
Mario Mariani, Carlo Cavallotti - Italy
DFT study of uranium and plutonium oxides in gas phase: structures and
thermodynamic properties
1210
Leonardo Trupinić, Nikola Pavlović, Renato Hohnjec - Croatia
Development of the probe for the Ultrasonic examination of tube butt welds with
tube wall thicknesses less than 8 mm
1211 Maddalena Negrin, Eros Mossini, Elena Macerata, Marta Cerini, Marco Giola,
Mario Mariani, Laura Pellegrini - Italy
Fuel-coolant chemical interaction in LFR systems: a preliminary thermodynamic
approach
1212
1213
Marjan Suban, Robert Planinc, Borut Bundara, Robert Cvelbar - Slovenia
The corrosion behaviour of dissimilar steel weld due to synergy of several effects:
Field case study
1214
Zhengxiang Chen, Leon Cizelj - China
Multiscale Simulations Of The Load Path Change By Different Hardening Laws In
The Framework Of Crystal Plasticity
1215
Marko Budimir, Channa Nageswaran, Liudas Mažeika - Croatia
High Sensitivity Ultrasonic NDE Method for Early Detection of Creep Damage in
Alloy Steel Steam Systems in Power Plants
1216
Michal Pöschl - Czech Republic
Development and Testing Richard Manipulator for NDE Applications
1217
Younjung Kim, Sunyeh Kang, Geeseok Kim, Hyunmin Kim, Daehee Lee - South Korea
A Methodology to Evaluate Stress in Surge Line from Outer Surface Temperature
for Fatigue Assessment
Alberto Tosolin, Elena Macerata, Eros Mossini, Marta Cerini, Marco Giola,
Mario Mariani - Italy
Formation Enthalpies estimation by a semi-empirical approach for chemical
considerations in Lead-cooled Fast Reactors
x23rd International Conference Nuclear Energy for New Europe
Program
Session 8
16:40
Radioactive waste and decommissioning
Chairpersons:
Tomaž Žagar, Slovenia
Irena Mele, Slovenia
16:40 805
Amine Bouhaddane, Gabriel Farkas, Vladimír Slugeň - Slovakia
MCNP calculations in connection to the decommissioning scenario
17:00 802
Juergen Skrzyppek, Stefan Fopp, Michael Köbl - Germany
A Well Established System for the Dry Storage of Spent Fuel
17:20 811
Peter Breitenstein, Cecile Evans - France
A global used fuel solution (Closing the nuclear fuel cycle for a utility or country
with a limited fleet and no confirmed new build program)
17:40 804
Sandi Viršek, Tomaž Žagar - Slovenia
Natural and Engineering Barriers – the Safety Concept Basis for LILW Repository
in Vrbina, Krško
23rd International Conference Nuclear Energy for New Europe xi
Program
Wednesday, September 10
Session 9
8:30
Thermal-hydraulics I
Chairpersons:
Iztok Tiselj, Slovenia
Francesco D’Auria, Italy
8:30 901 Andrej Prošek, Andrija Volkanovski - Slovenia
Mitigation Strategy for Extended Blackout Power Condition
8:50 908 Jure Oder, Matej Tekavčič, Iztok Tiselj - Slovenia
Simulations of condensation induced slug formation and slug acceleration in
partially filled elbow shaped geometry
9:10 903 Andrea Querol, Sergio Gallardo, Gumersindo Verdú - Spain
Analysis of CET and PCT during a SBLOCA. Application to a scaled-up model
Session 10
9:50
Thermal-hydraulics II
Chairpersons:
Iztok Tiselj, Slovenia
Francesco D’Auria, Italy
9:50
904
Young Seok Bang, Sweng Woong Woo, Min Jeong Hwang, S.K. Sim - South Korea
Best Estimate Calculation and Uncertainty Evaluation of LBLOCA of APR+
Considering New Safety Features
10:10 905
Martin Draksler, Boštjan Končar, Leon Cizelj, Bojan Ničeno - Slovenia
Instantaneous Heat Transfer Characteristics of Multiple Impinging Jets
10:30 906
Tadeja Polach, Miha Lenič, Ivica Bašić, Luka Štrubelj - Slovenia
NEK Small Break LOCA Simulation by APROS code
Session 11
11:10
Nuclear power plant operation
Chairpersons:
Bruno Glaser, Slovenia
Jose Manuel Garcia Cerecedo, Spain
11:10 1012 Zdenko Kovačić, Matko Orsag, Borislav Balac, Stjepan Flegarić,
Kristijan Brkić, Ante Mamić - Croatia
Autonomous Mobile Robots for Deep and Shallow Hydrodynamic Treatment
of Concrete and Metal Surfaces
11:30 1002 Pavel Omahen - Slovenia
Capacity and Reliability of Slovenian Transmission Grid in Light of a Future
Reasonable Production Increase from Krško NPP Units
11:50 1003 Harri Tuomisto - Finland
Deploying Experiments to Support Internal Hazard Management
12:10 1004 György Hegyi, Andras Kereszturi, István Trosztel - Hungary
ATHLET/KIKO3D results of the OECD/NEA benchmark for coupled codes on
KALININ-3NPP measured data
xii23rd International Conference Nuclear Energy for New Europe
Program
Thursday, September 11
8:30
Invited lecture
103
Session 12
Francesco Romanelli - United Kingdom
The European Fusion Roadmap
9:10
Nuclear fusion
Chairpersons:
Tomaž Gyergyek, Slovenia
Boštjan Končar, Slovenia
9:10
9:30
9:50
1112
1108
1103
Aleksander Drenik, Rok Zaplotnik, Gregor Primc, Miran Mozetič, Anže Cigoj Slovenia
Laboratory Experiments of Ammonia Production in Plasmas of H2 – N2 Mixtures
Ivan Aleksander Kodeli, Vladimir Radulović, Darko Kavšek, Władysław Pohorecki,
Tadeusz Kuc - Slovenia
Sensitivity and Uncertainty Pre-analysis of the FNG Copper 14 MeV DT Benchmark
for Fusion Relevant Cross-Section Validation
Igor Lengar, Luka Snoj, Aljaž Čufar, Brian Syme, Paola Batistoni, Sean Conroy Slovenia
Characterization of the neutron field for the JET torus
10:10 1104 Anže Založnik, Sabina Markelj, Iztok Čadež - Slovenia
Hydrogen atom recombination study on W by vibrational spectrometer in
differential pumping mode
Session 13
10:50
Materials, integrity and life management
Chairpersons:
Leon Cizelj, Slovenia
Tim Haste, France
10:50 1201 Hygreeva Kiran Namburi, Petra Bublíková, Vít Rosnecký, Jan Michalička,
Eliška Keilová, Jan Kočík, Miroslava Ernestová - Czech Republic
TEM Foils Preparation from Irradiated Austenitic Stainless Steel ‒ An applied
methodology to attain 1mm samples
11:10 1202 Cecile-Aline Gosmain, Sylvain Rollet, Michel Tommy-Martin, Isabelle Rupp,
Jean-Luc Flejou - France
Impact on Neutronic Calculation of Thermomechanical Expansion of Reactor
Vessel Internals
11:30 1203 Igor Simonovski, Oliver Martin, Gangadhar Machina, Szabolcs Szavai,
Robert Beleznai - Netherlands
K/J value estimation of specimen containing dissimilar metal welds
11:50 1206 Tomislav Tomašić, Andrej Jokić, Ante Bakić - Croatia
Automated Motion of the Forerunner Mobile Manipulator Over the Tube Sheets
12:10 1205 Samir El Shawish, Leon Cizelj - Slovenia
Extended Crystal Plasticity Finite Element Approach for Neutron Irradiated
Austenitic Stainless Steels
23rd International Conference Nuclear Energy for New Europe xiii