atw 2018-1

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atw Vol. 63 (2018) | Issue 1 ı January 50 AMNT 2018 Experimental and Theoretical Investigation of Boiling in the Slightly Inclined Tubes of the Containment Cooling Condenser | | Frances Viereckl, TU Dresden, Chair of Hydrogen and Nuclear Energy, Germany Model Order Reduction of Low Pressure Natural Circulation System | | René Manthey, TU Dresden, Institute of Power Engineering, Germany Model Order Reduction of a High Pressure Natural Circulation System | | Alexander Knospe, TU Dresden, Institut für Energietechnik, Germany New Neutron Kinetic Developments and Findings Chair: | | Dr. Tatiana Salnikova Keynote Insights of End-of-Life Core Design from Utility Point of View | | Dr. Marcus Seidl, PreussenElektra GmbH, Germany Frequency-Domain Investigation on the Neutron Noise in KWU PWRs | | Marco Viebach, TU Dresden, Institut für Energietechnik, Germany Nuclear Energy Campus The Nuclear Energy CAMPUS leads through the world of radioactivity, nuclear technology and radiation protection with individual stations. There will be contact persons available at all of the themed stands to offer information in form of short talks, movies, demonstrations or experiments. Besides, information on study options and career perspectives within nuclear industry are provided. The CAMPUS language will be German.. Welcome and Introduction | | Florian Gremme, Young Generation Network, KTG, Germany Post-Test Analysis of the RPV Lower Head Leak Experiment at the INKA Test Facility Using ATHLET | | Michael Sporn, TU Dresden, Institute of Power Engineering, Germany New Thermal Hydraulic Development and Findings Chair: | | Dr. Sanjeev Gupta Keynote International Cooperation in the Experimental Field of Nuclear Thermohydraulics: Primary Coolant Loop Test Facility (PKL) | | N.N., OECD, France Keynote International Cooperation on Pool Scrubbing Research: Examples of NUGENIA/IPRESCA Project | | Dr. Sanjeev Gupta, Becker Technologies GmbH, Germany Application of an Eulerian/Eulerian CFD Approach to Simulate the Thermohydraulics of Rod Bundles | | Dr. Wei Ding, Helmholtz Zentrum Dresden Rossendorf, Germany Analysis of the Fatigue of the Bolts in the Flange of a Reactor Pressure Vessel | | Fabian Gottlieb, Kraftanlagen Heidelberg GmbH, Technical Analysis, Germany Preliminary Results of Water Hammer Simulation in Two-Phase Flow Regimes Using the Code ATHLET 3.1A | | Christoph Bratfisch, Ruhr-Universität Bochum, Germany Design of Simplified and Optimized Heavy Liquid Metal Loop for Future Applications | | Dr.-Ing. Nader Ben Said, Westinghouse Electric Germany GmbH, Germany Investigation on Variation of Nodelized Macroscopic Cross Sections Driven by Deflection of Fuel assemblies with Serpent | | Nico Bernt, Technische Universität Dresden (TUD), Germany PWR Cycle Analysis With the GRS Core Simulator KMACS | | Dr. Matías Zilly, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany Application of a Full-Core Statistical Approach in LB-LOCA Analysis | | Dr. Andreas Wensauer, PreussenElektra GmbH, Germany Nuclear Data Uncertainty Analyses with XSUSA and MCNP | | Dr. Winfried Zwermann, Gesellschaft für Anlagenund Reaktorsicherheit (GRS) gGmbH, Germany Workshop Young Scientists' Workshop Tuesday ı 29 th May 2018 Wednesday ı 30 th May 2018 Coordinator: | | Prof. Dr.-Ing. Jörg Starflinger, University of Stuttgart, Germany Jury: | | Prof. Dr. Marco K. Koch, Ruhr-Universität Bochum | | Prof. Dr. Jörg Starflinger, University of Stuttgart, Institut für Kernenergetik und Energiesysteme (IKE) | | Dr. Wolfgang Steinwarz | | Dr. Katharina Stummeyer, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH Prize awarded by: | | GNS Gesellschaft für Nuklear-Service mbH and Forschungsinstitut für Kerntechnik und Energiewandlung e. V. Introducing of the Young Generation Network | | Yvonne Schmidt-Wohlfarth, Young Generation Network, KTG, Germany Nuclear Technology in and Beyond our Daily Lifes | | N.N. Working in NPPs | | Sebastian Hahn, Young Generation Network, KTG, Germany Radioactivity and Radiation Protection | | Sven Jansen, VKTA – Strahlenschutz, Analytik & Entsorgung Rossendorf e. V., Germany Final Disposal of Radioactive Waste | | Dr. Thilo von Berlepsch (BGE), Germany Nuclear Fusion | | André Häußler, Elena Nunnemann, Karlsruhe Institute of Technology (KIT), Germany Stations of Nuclear Campus 1 NPPs & Decommissioning 2 Electricity Market – Composition of the Electricity Price 3 Packaging, Casks & Conditioning of Waste 4 Nuclear Medicine Applications Modeling of Post-Dryout Heat Transfer | | Dali Yu, Karlsruhe Institute of Technology (KIT), Germany Detailed session programme to be announced. AMNT 2018 Preliminary Programme
atw Vol. 63 (2018) | Issue 1 ı January Key Topic Enhanced Safety & Operation Excellence Focus Sessions Tuesday ı 29 th May 2018 Radiation Protection during decommissioning – are there special needs? Coordinators: | | Eric Baumann, New NP GmbH, Germany Dr. Angelika Bohnstedt, Karlsruhe Institute of Technology (KIT), Germany The first area of the session addresses protection of personnel engaged in decommissioning activities. Decommissioning activities are associated with large changes in the NPP configuration. The overall remaining radioactive inventory will shift. Systems are taken out of service. Originally confined radioactive sources become open sources due to the fact that systems are decommissioned. Demolition of civil structures and other unit elements require additional technical systems to cope with air contamination. The second area of discussion deals with clearance of radioactive material and public acceptance. A large amount of medium and low level waste has to be examined and removed from the site. This topic also addresses the question of “conditional” and “ unconditional” release of components and material. It is not only a question about clearance levels but also about public acceptance of receiving cleared, i.e. non-nuclear, waste at normal landfill sites. To all decommissioning activities, the ALARA approach applies. German rules and regulations, e.g. Radiation Protection Ordinance, various KTA rules, and international rules (BSS) and recommendations issued e.g. by IAEA or EU provide an appropriate framework for workers protection. Is there a need for specific “German decommissioning rules”? The final closure of a site requires the removal of all material. The largest amount originating from the demolition of buildings is non-nuclear waste. Some amount of waste has gone through the clearance. Some amount of waste was never subject to nuclear regulatory surveillance because it originates from office buildings, cooling towers, turbine buildings (in PWR plants), pumping station structures and others. Beside construction waste, valuable raw materials are extracted – e.g. copper from electrical cables. How is the public acceptance of “evil stuff” from a nuclear power plant? This session tries addressing some of these questions and tries providing some answers. Some of the presentation will give an interesting introduction and the answer might be gained during lively discussions between the session participants. Detailed session programme to be announced. International Operational Experience Coordinator: | | Dr.-Ing. L. Mohrbach, VGB PowerTech e.V., Germany The operation of nuclear power plants involves a wide scope of specialized areas of expertise, from materials to human factors. Beyond daily business, some background information from different fields of operational activities might not only be regarded as personally worthwhile but may also be well suited to complement the general knowledge base for nuclear. This session addresses some of these questions and tries providing some answers. Some of the presen tations will give an introduction and produce questions. The answer might be gained during lively discussions between the session participants. Summary of the QUENCH LOCA Experimental Program | | Dr. Andreas Wensauer, PreussenElektra GmbH, Germany Practical Safeguards in Nuclear Power Plants | | Dr. Irmgard Niemeyer, Dipl.-Ing. Katharina Aymanns, Forschungszentrum Jülich GmbH, Germany (TBC) Comparison of Employment Effects of Low-Carbon Generation Technologies | | Geoffrey Rothwell, OECD Nuclear Energy Agency (NEA), France Application of Lubricants and other Consumables in Nuclear Power Plants | | Dr. Fred Böttcher, EnBW Kernkraft GmbH; Dr. Dittmar Rutschow, VGB PowerTech e. V., Germany New Developments in Radiation Protection | | N.N. Benefits of Simulator Training | | N.N., KSG Kraftwerks-Simulator- Gesellschaft mbH, GfS Gesellschaft für Simulatorforschung mbH, Germany Technical Sessions Wednesday ı 30 th May 2018 Operation and Safety of Nuclear Installations Chair: | | Dr. Thorsten Hollands Keynote Coordinator: | | Dr. Erwin Fischer Chair: | | Dr. Thorsten Hollands Keynote Safe to the Last Day – A Challenge for Operators | | Christoph Heil, EnBW Kernkraft GmbH, Executive Director, Germany Keynote Is Safety Culture Perceptible and Measurable? | | Uwe Stoll, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Scientific and Technical Director, Germany Keynote Preserving and Ensuring Competence and Motivation | | Dr. Frank Sommer, PreussenElektra GmbH, Head of CoC Operations, Germany Digital Transformation in Nuclear Industry – Focus: Site Applications | | Dr. Jan Leilich, New NP, IBGM Product Management, Germany Save to the Last Day – How to Manage the Complexity in a Multi-Year End of Life Process | | Prof. Dr. Rüdiger von Der Weth, Hochschule für Wirtschaft und Technik Dresden, Faculty of Business Administration, Germany Loca Scenario-Related Zinc Borate Precipitation Studies at Lab Scale | | Dr. Ulrich Harm, Technische Universität Dresden (TUD), Germany Simulation of Asymmetric Severe Accidents Using the Code System AC2 | | Liviusz Lovasz, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany Simulation of the Bundle Test QUENCH-07 with the Severe Accident Analysis Codes ASTEC V2.1 and AC^2 – ATHLET CD | | Florian Gremme, Ruhr-Universität Bochum, Chair of Energy Systems and Energy Economics, Germany Sensitivity and Uncertainty Analysis of the MCCI Model Results in AC2/COCOSYS for the OECD-CCI3 Experiment | | Dr. Claus Spengler, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany Dry Filter Method DFM 2.0 – The Newest Generation of Filtered Containment Venting System | | Dr. Peter Hausch, Caverion Deutschland GmbH, Business Unit Krantz, Germany 3D Surface Radiation Dosimetry of a Nuclear-Chicago NH3 Neutron Howitzer | | Ahmet Ilker Topuz, Istanbul Technical University, Nuclear Energy, Turkey Chair: Dr. Jürgen Sydow TESPA-ROD Code Prediction of the Fuel Rod Behaviour During Long-Term Storage | | Dr. Heinz-Günther Sonnenburg, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Germany 51 AMNT 2018 AMNT 2018 Preliminary Programme
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