Conference Timetable - Nuclear Society of Slovenia
Transcription
Conference Timetable - Nuclear Society of Slovenia
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