Proceedings

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The country, displayed next to the names of authors, is the country of the first author. In some cases authors are coming from different countries.

Invited lectures

No. 101
Nuclear energy, an energy for the future
Christophe Behar - France

No. 102
Finnish approach for synergistic effects of research, reliability and safety in nuclear energy
Rauno Rintamaa - Finland

No. 103
The European Fusion Roadmap
Francesco Romanelli - Italy
 
Nuclear energy and society
No. 201

Nuclear Industry and European BSS
Helena Janžekovič - Slovenia

No. 203

New Training Experiments at the JSI TRIGA Mark II Reactor
Luka Snoj, Sebastjan Rupnik, Anže Jazbec - Slovenia

No. 204

Improving nuclear literacy through e-communication: the “eWorld” web project
Melita Lenošek Kavčič, Mojca Drevenšek, Rok Rožman - Slovenia

No. 206

Travelling Exhibition Fusion Expo
Tomaž Skobe - Slovenia

No. 207

Nuclear Power Plant Krško 2 Action Plan
Žiga Arnšek, Tomaž Ploj, Jože Špiler - Slovenia

No. 208

Public Opinion about Nuclear Energy – Year 2014 Poll
Radko Istenič, Igor Jenčič - Slovenia

No. 209

Public opinion and nuclear energy: INPRO methodology and recent findings in the open literature
Rolando Calabrese - Italy

No. 211

Regulatory oversight of activities following the discovery of damaged fuel assemblies during the Krško NPP outage 2013
Tomaž Nemec, Andrej Stritar - Slovenia

No. 212

Sensitivity analyses to support determination of emergency planning zones around the Krško nuclear power plant
Andrej Stritar, Barbara Vokal Nemec, Tomaž Nemec, Michel Cindro, Jernej Györköš, Dušan Peteh, Marjan Tkavc - Slovenia

No. 214

ALARA in Practice
Matjaž Koželj - Slovenia

No. 215

Bid Technical Evaluation Process for JEK 2 Project
Aleš Kelhar, Jurij Kurnik, Klemen Debelak, Robert Bergant - Slovenia

 
Severe accidents
No. 301

Iodine Benchmarks in the SARNET2 Network of Excellence
Tim Haste, Mirco Di Giuli, Gunter Weber, Sebastian Weber - France

No. 302

Application of Thermal Hydraulic and Severe Accident Code SOCRAT/V3 to Bottom Water Reflood Experiment QUENCH-LOCA-1
Alexander D. Vasiliev, Juri Stuckert - Russian Federation

No. 303

Influence of Zirconium Oxidation on Steam Explosion Energetics
Matjaž Leskovar, Mitja Uršič, Vasilij Centrih, Pascal Piluso, Nathalie Cassiault-Louis, Claude Brayer, Vaclav Tyrpekl - Slovenia

No. 305

Analysis of CABRI-BI1 loss-of-flow experiment using ASTEC-Na
Alain Flores Y Flores, Vaidas Matuzas, Luca Ammirabile - Netherlands

No. 306

Spatial Distribution of Hydrogen in NEK Containment
Davor Grgić, Tomislav Fancev, Siniša Šadek, Vesna Benčik - Croatia

No. 308

Analysis of Stratified Steam Explosions
Matjaž Leskovar, Vasilij Centrih - Slovenia

No. 309

Simulation of THAI Hydrogen Deflagration Experiments with Upward Flame Propagation in Homogeneous Atmosphere using ASTEC Severe Accidents Code
Ivo Kljenak - Slovenia

No. 311

Development of the Post-Accident Strategy after the Nuclear or Radiological Accident
Helena Janžekovič, Andrej Stritar, Darja Slokan Dušič, Marjan Tkavc, Barbara Vokal Nemec - Slovenia

No. 312

SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission products behaviour
Mirco Di Giuli, Tim Haste, Regis Biehler - Italy

No. 313

Pressurized Water Small Modular Reactor (SMR) Modelization and Severe Accident Analysis using ASTEC code
Mirco Di Giuli, Marco Sumini, Giacomino Bandini - Italy

No. 314

Transition boiling modelling in the MC3D code
Mitja Uršič, Renaud Meignen, Gabrijela Ikovic - Slovenia

 
Multiphysics
No. 401

Analysis of Thermalhydraulic Fluctuations in Trillo NPP with CTF/PARCSv2.7 Coupled Code
Agustin Abarca, Rafael Miró, Gumersindo Verdú - Spain

No. 402

Neutronics and Thermal-hydraulics Study on Maximizing In Situ Utilization of U-233 in the Th-U5-fueled HTR-PM
Bing Xia, Fu Li, Chunlin Wei, Fubing Chen - China

No. 403

Optimization of an integrated neutronic/thermal-hydraulic reactor core analysis model
Antonios Mylonakis, Melpomeni Varvayanni, Dimokratis Grigoriadis, Panayiota Savva, Nicolas Catsaros - Greece

No. 404

Coupling the ATHLET3.0 and the KIKO3DMG multigroup 3D kinetic code developed for the fast spectrum Gen4 reactors
György Hegyi, Andras Kereszturi, István Pataki, Ádám Tóta, Kiril Velkov, Ihor Pasichnyk, Yann Périn - Hungary

No. 405

Peach Bottom Low Flow Stability Analysis with TRACE/PARCS
Consuelo Gómez-Zarzuela, Teresa Barrachina, Agustin Abarca, Rafa Miró, Gumersindo Verdú - Spain

No. 406

A new coupling CFD/Monte Carlo neutron transport scheme, Application to a single fuel rod problem
Romain Henry, Iztok Tiselj - Slovenia

 
Probabilistic safety assessment
No. 501

Evaluation of dependency of human errors in PSA
Jan Prochaska - Slovakia

No. 502

Benefits Of Robustness Analysis - Robustness Case Studies in European NPP´s
Peter Schimann, Zoran Stošić - Germany

No. 503

Overview of Fire PSA and supporting software
Peter Simurka - Slovakia

No. 505

PSA analyses of mitigation strategies for extreme external events
Blaže Gjorgiev, Andrija Volkanovski - Slovenia

No. 506

Assessment of Loss of Offsite Power Initiating Event Frequency
Marko Čepin - Slovenia

 
Reactor physics
No. 601

Evaluation of the efectiveness of a simple GFR2400 heterogenous control rod design
Stefan Cerba, Branislav Vrban, Jakub Lüley, Vladimir Nečas - Slovakia

No. 602

Verification of Power Distribution of real fuel loadings in VVER-440 reactor
Branislav Vrban, Stefan Cerba, Gabriel Farkas, Ján Haščík, Jakub Lüley, Vladimir Nečas, Peter Urban - Slovakia

No. 603

Simulation of the NPP Krško startup core with CASL core simulator, VERA-CS
Fausto Franceschini, Marjan Kromar, Dušan Ćalić, Andrew Godfrey, Benjamin Collins, Thomas Evans, Jess Gehin - USA

No. 605

Computational study of neutron screens performance considering different absorbing materials
Nefeli Chrysanthopoulou, Gregory Delipei, Panayiota Savva, Melpomeni Varvayanni, Nicolas Catsaros - Greece

No. 606

Determination of Isotopic Composition due to Fuel Cooling after Outage with the use of Isotopic Factors
Dušan Ćalić, Andrej Trkov, Marjan Kromar - Slovenia

No. 607

Modeling of PWR Biological Shield Boration Using SCALE6.1 Hybrid Shielding Methodology
Mario Matijević, Dubravko Pevec, Krešimir Trontl - Croatia

No. 608

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
Antonia Labarile, Rafael Miró, Nicolás Olmo, Agustin Abarca, T. Barrachina, Gumersindo Verdú - Spain

No. 609

Windows interface environment XSUN-2013 for NEA transport and sensitivity-uncertainty computer codes TRANSX-2, PARTISN and SUSD3D
Slavko Slavič, Ivan Kodeli - Slovenia

No. 610

Evaluation of the Point Kinetic Model of NEK in APROS
Tadeja Polach, Ivica Bašić, Luka Štrubelj - Slovenia

No. 611

Scale 6.1 evaluation of the effective cross sections of a LWR assembly-reflector model with application to the NEA TMI-1 PWR Benchmark
Federico Rocchi, Marco Sumini, Antonio Guglielmelli - Italy

No. 612

Reactor Physics Analysis of the Krško NPP by JSI and Westinghouse
Marjan Kromar, Fausto Franceschini - Slovenia

No. 613

Fluence Rate Benchmarking of the Stochastic Neutronic Code ANET
Thalia Xenofontos, Gregory Delipei, Panayiota Savva, Melpomeni Varvayanni, Nicolas Catsaros, Jacques Mailliard, Jorge Silva - Greece

No. 614

VENUS-2 MOX Core Benchmark Analysis using MCNP5 1.40 with JEFF 3.1.2 and ENDF/B-VII.0 nuclear data sets
Gregory Delipei, Panayiota Savva, Melpomeni Varvayanni, Nicolas Catsaros - Greece

 
Research reactors
No. 701

Fuel Burnup Calculation in ITU TRIGA Mark II Research Reactor by Using Monte Carlo Method
Mehmet Türkmen, Üner Çolak - Turkey

No. 702

Measurements of the in-core neutron flux distribution and energy spectrum at the TRIGA Mark II reactor of the Vienna University of Technology/Atominstitut
Marcella Cagnazzo, Christina Raith, Mario Villa, Helmuth Böck - Austria

No. 703

Thermal Power Calibration of the TRIGA Mark II Reactor
Žiga Štancar, Luka Snoj - Slovenia

No. 704

MARIA Research Reactor Thermalhydraulic Calculations With RELAP5 Code.
Eleonora Skrzypek, Maciej Skrzypek, Krzysztof Gomulski - Poland

No. 705

Calculations to support design and installation of the DT Converter in TRIGA Mark-II
Aljaž Kolšek, Luka Snoj, Patrick Sauvan - Slovenia

No. 706

Validation of the neutron and gamma flux distributions in the JSI TRIGA reactor core
Gašper Žerovnik, Tanja Kaiba, Vladimir Radulović, Anže Jazbec, Sebastjan Rupnik, Loic Barbot, Damien Fourmentel, Luka Snoj, Jean-François Villard - Slovenia

No. 707

Determination of Computational Bias for Sub-critical Configuration of VR-1
Jakub Lüley, Stefan Cerba, Ján Haščík, Branislav Vrban, Vladimir Nečas, Jan Rataj, Ondřej Huml - Slovakia

No. 708

Physical Analysis of Thermalization in Thermal Column Irradiation Position
Aljaž Kolšek, Luka Snoj - Slovenia

No. 709

Comparison of Measured and Calculated Reactivity-Worth Curves of Control Rods in a TRIGA Reactor
Vid Merljak, Andrej Trkov, Igor Lengar - Slovenia

No. 710

Kinetic Simulation of Control Rod Reactivity Worth Measurement in a TRIGA Reactor by the Rod-Drop Method
Vid Merljak, Andrej Trkov, Marjan Kromar - Slovenia

No. 711

Analysis of neutron flux and reaction rates of TRIGA research reactor using Monte Carlo code Serpent
Dušan Ćalić, Gašper Žerovnik, Luka Snoj, Andrej Trkov - Slovenia

No. 712

Application of best estimate plus uncertainty in review of research reactor safety analysis
Simon Adu, Ivan Horvatovic, Francesco D'Auria - Ghana

 
Radioactive waste and decommissioning
No. 802

A Well Established System for the Dry Storage of Spent Fuel
Juergen Skrzyppek, Stefan Fopp, Michael Köbl - Germany

No. 804

Natural and Engineering Barriers – the Safety Concept Basis for LILW Repository in Vrbina, Krško
Sandi Viršek, Tomaž Žagar, Matthew Kozak - Slovenia

No. 805

MCNP calculations in connection to the decommissioning scenario
Amine Bouhaddane, Gabriel Farkas, Vladimír Slugeň - Slovakia

No. 808

Optimization of the Vrbina LILW Repository Preliminary Design
Boštjan Duhovnik, Janja Špiler - Slovenia

No. 810

The Solidification of Liquid Radioactive Waste – New Technique and Knowledge Applied in Institutional Waste Management in Slovenia
Marko Kostanjevec, Simona Sucic - Slovenia

 
Thermal-hydraulics
No. 901

Mitigation Strategy for Extended Blackout Power Condition
Andrej Prošek, Andrija Volkanovski - Slovenia

No. 903

Analysis of the Core Exit Temperature and the Peak Cladding Temperature during a SBLOCA. Application to a scaled-up model.
Andrea Querol, Sergio Gallardo, Gumersindo Verdú - Spain

No. 904

Best Estimate Calculation and Uncertainty Evaluation of LBLOCA of APR+ Considering New Safety Features
Young Seok Bang, Sweng Woong Woo, Suk K. Sim, Min Jeong Hwang - South Korea

No. 905

Instantaneous Heat Transfer Characteristics of Multiple Impinging Jets
Martin Draksler, Boštjan Končar, Leon Cizelj, Bojan Ničeno - Slovenia

No. 907

Code-to-code comparison of the VVER 440/V213 containment response to the DBA
Ján Kubačka, Peter Juriš, Martin Gajdoš - Slovakia

No. 908

Simulations of condensation induced slug formation and slug acceleration in partially filled elbow shaped geometry
Jure Oder, Matej Tekavčič, Iztok Tiselj - Slovenia

No. 909

RELAP5 analysis of Krško nuclear power plant abnormal event from 2011
Andrej Prošek, Marko Matkovič - Slovenia

No. 910

Supporting Deterministic T-H Analyses for Level 1 PSA
Slavomir Bebjak, Tomas Kliment - Slovakia

No. 911

Steam Generator Modeling in Apros
Klemen Debelak, Tadeja Polach, Luka Štrubelj - Slovenia

No. 912

Modeling of Low Pressure Injection System of NEK in computer code APROS
Jure Jazbinšek, Luka Štrubelj, Ivica Bašić - Slovenia

No. 914

Capability of TRANSURANUS code to reproduce LOCA integral test results
Oleksandr Lisovyy, Marco Cherubini, Francesco D'Auria - Italy

No. 915

Development Status for Krško NPP TRACE Model with Three Dimensional Pressure Vessel
Ovidiu-Adrian Berar, Andrej Prošek, Borut Mavko - Slovenia

No. 916

Simulation of flooding waves in vertical air-water churn flow using Neptune_CFD 2.2.0 code
Matej Tekavčič, Boštjan Končar, Ivo Kljenak - Slovenia

No. 917

Dynamic Simulation of NEK Reactor Coolant Pump with Best Estimate Full Scale Model in APROS
Dejan Slovenc, Samo Fürst, Ivica Bašić - Slovenia

No. 918

Upper plenum temperature calculations: comparison of TRANSURANUS with a 2–D model under steady–state conditions
Rolando Calabrese, Arndt Schubert, Paul Van Uffelen, Luka Vlahovic, Csaba Gyori - Italy

No. 919

Investigation of coolant temperature fluctuations circulating in the primary circuit of VVER-440 reactors
Sándor Kiss, Sándor Lipcsei - Hungary

No. 920

Numerical simulations of a turbulent flow in a fuel assembly
Blaž Mikuž, Iztok Tiselj - Slovenia

 
Nuclear power plant operation
No. 1001

Krško NPP 2nd Periodic Safety Review Lessons Learned
Ivica Bašić, Ivan Vrbanić, Aleksandra Antolovič, Bruno Glaser - Croatia

No. 1002

Capacity and Reliability of the Slovenian Transmission Grid in Light of a Future Reasonable Production Increase from Krško NPP Units
Pavel Omahen - Slovenia

No. 1003

Deploying Experiments to Support Internal Hazard Management
Harri Tuomisto - Finland

No. 1004

ATHLET/KIKO3D results of the OECD/NEA benchmark for coupled codes on KALININ-3NPP measured data
György Hegyi, Andras Kereszturi, István Trosztel, Zsolt Elter - Hungary

No. 1005

Historical Review of Exposure due to the C-14 Discharges from the Krško NPP
Milko Križman, Matjaž Stepišnik - Slovenia

No. 1007

Post-Fukushima Assessment of the AP1000® Plant
Bryan Friedman, Adam Malinowski, Ernesto Boronat De Ferrater - USA-Pensylvania

No. 1008

Quality Assurance Oversight of Important Plant Functional Areas
Igor Fifnja, Janez Novak - Slovenia

No. 1010

Neutron noise analysis in the NPP Krško
Marjan Kromar, Bojan Kurinčič, Urban Simončič - Slovenia

No. 1012

Autonomous Mobile Robots for Deep and Shallow Hydrodynamic Treatment of Concrete and Metal Surfaces
Zdenko Kovacic, Matko Orsag, Borislav Balać, Stjepan Flegaric, Kristijan Brkic, Ante Mamic - Croatia

No. 1013

RJET – 111: Autonomous Mobile Robot for Water Intake Channel Maintenance in Power Plant Cooling Systems
Matko Orsag, Zdenko Kovacic, Stjepan Flegaric, Kristijan Brkic, Zeljko Bastalic-Bestak, Borislav Balać - Croatia

 
Nuclear fusion
No. 1102

TRIGA Irradiations of Mn foils and TLD as Potential Tritium Production Monitors for Fusion Applications
Ivan Kodeli, Vladimir Radulović, Darko Kavsek, Władysław Pohorecki, Tadeusz Kuc - Slovenia

No. 1104

Hydrogen atom recombination study on W by vibrational spectrometer in differential pumping mode
Anže Založnik, Sabina Markelj, Iztok Čadež - Slovenia

No. 1106

On the Role of the Source Term in a Fluid Model of the Sheath Formation in an Oblique Magnetic Field
Tomaž Gyergyek, Jernej Kovačič - Slovenia

No. 1107

Ion Energy Analyzer Particle Simulation
Lojze Gačnik, Jernej Kovačič, Tomaž Gyergyek - Slovenia

No. 1108

Sensitivity and Uncertainty Pre-analysis of the FNG Copper 14 MeV DT Benchmark for Fusion Relevant Cross-Section Validation
Ivan Kodeli, K. Kondo, A. Klix, Ulrich Fischer, M. Angelone - Slovenia

No. 1109

Visualization schema for fusion data structures
Leon Kos, Girish Ramesh - Slovenia

 
Materials, integrity and life management
No. 1201

TEM Foils Preparation from Irradiated Austenitic Stainless Steel -An applied methodology to attain 1mm samples
Hygreeva Namburi, Petra Bublíková, Vít Rosnecký - Czech Republic

No. 1202

Impact on Neutronic Calculation of Thermomechanical Expansion of Reactor Vessel Internals
Cecile-Aline Gosmain, Charlotte Sandrin, Michel Tommy-Martin, Isabelle Rupp, Jean-Luc Flejou - France

No. 1203

J value estimation of specimen containing dissimilar metal welds
Igor Simonovski, Oliver Martin, Gangadhar Machina, Szabolcs Szavai, Robert Beleznai - Netherlands

No. 1205

Extended Crystal Plasticity Finite Element Approach for Neutron Irradiated Austenitic Stainless Steels
Samir El Shawish, Leon Cizelj, Benoit Tanguy, Xu Han, Jeremy Hure - Slovenia

No. 1206

Automated Motion of the Forerunner Mobile Manipulator Over the Tube Sheets
Tomislav Tomašić, Andrej Jokić, Ante Bakic - Croatia

No. 1208

Uncertainties in Fatigue Life Assessment of Pipes due to Random Thermal Loads
Oriol Costa Garrido, Samir El Shawish, Leon Cizelj - Slovenia

No. 1209

DFT study of uranium and plutonium oxides in gas phase: structures and thermodynamic properties
Marta Cerini, Giuseppe Dia, Elena Macerata, Eros Mossini, Marco Giola, Mario Mariani, Carlo Cavallotti - Italy

No. 1210

Development of the probe for the Ultrasonic examination of tube butt welds with tube wall thicknesses less than 8 mm
Leonardo Trupinić, Nikola Pavlović, Renato Hohnjec - Croatia

No. 1211

Fuel-coolant chemical interaction in LFR systems: a preliminary thermodynamic approach
Maddalena Negrin, Eros Mossini, Elena Macerata, Marta Cerini, Marco Giola, Mario Mariani, Laura Pellegrini - Italy

No. 1212

Formation Enthalpies estimation by a semi-empirical approach for chemical considerations in Lead-cooled Fast Reactors
Alberto Tosolin, Elena Macerata, Eros Mossini, Marta Cerini, Marco Giola, Mario Mariani - Italy

No. 1213

The corrosion behaviour of dissimilar steel weld due to synergy of several effects: Field case study
Marjan Suban, Robert Planinc, Robert Cvelbar, Borut Bundara - Slovenia

No. 1215

High Sensitivity Ultrasonic NDE Method for Early Detection of Creep Damage in Alloy Steel Steam Systems in Power Plants
Marko Budimir, Channa Nageswaran, Liudas Mažeika - Croatia

No. 1217

A Methodology to Evaluate Stress in Surge Line from Outer Surface Temperature for Fatigue Assessment
Younjung Kim, Sunyeh Kang, Geeseok Kim, Hyunmin Kim, Daehee Lee - South Korea