Enhanced Safety & Operation Excellence

Focus Session

Tuesday, 29 May 2018, 14:00 – 17:30

Coordinators: Erik Baumann, Framatome GmbH, Germany and Dr. Angelika Bohnstedt, Karlsruhe Institute of Technology (KIT), Germany

 

Radiation Protection During Decommissioning – Are There Special Needs?

The 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. The second area of discussion deals with clearance of radioactive material and public acceptance. This topic 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. 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.

 

TitleSpeaker
14:00

Alpha Radiation Protection During the Dismantling of the Research Site in Dresden-Rossendorf

Dr. Dietmar Schlösser, Sven Jansen, Dr. Reinhard Knappik, VKTA - Strahlenschutz, Analytik & Entsorgung Rossendorf e. V., Germany

14:30Freigabeverfahren – Aktuelle Änderungen und HerausforderungenDr. Stefan Thierfeldt, Brenk Systemplanung GmbH, Germany
15:00Optimizing D&D by State-Of-The-Art Radiological CharacterizationLars Ackermann, Framatome GmbH, Germany
15:30Break
16:00Lessons Learned – Überraschungen bei der radiologischen Charakterisierung und FreigabeMatthias Bothe, VKTA - Strahlenschutz, Analytik & Entsorgung Rossendorf e.V.
16:30Entsorgung von freigegebenen Reststoffen – die Rolle des StrahlenschutzesDr. Stefan Thierfeldt, Brenk Systemplanung GmbH, Germany
17:00End of Session

Subject to change.

Tuesday, 29 May 2018, 14:00 - 17:30

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.

TitleSpeaker
14:00Summary of the QUENCH LOCA Experimental ProgramDr. Andreas Wensauer, PreussenElektra GmbH, Germany
14:30Practical Safeguards in Nuclear Power PlantsDr. Irmgard Niemeyer, Dipl.-Ing. Katharina Aymanns, Forschungszentrum Jülich GmbH, Germany (TBC)
15:00Comparison of Employment Effects of Low-Carbon Generation Technologies

Geoffrey Rothwell, OECD Nuclear Energy Agency (NEA), France

15:30Break
16:00Application of Lubricants and other Consumables in Nuclear Power PlantsDr. Fred Böttcher, EnBW Kernkraft GmbH, (TBC)
16:30New Developments in Radiation ProtectionN.N.
17:00Benefits of Simulator TrainingN.N., KSG Kraftwerks-Simulator-Gesellschaft mbH, GfS Gesellschaft für Simulatorforschung mbH
17:30End of Session

Subject to change.

Technical Session

 

Wednesday, 30 May 2018, 09:00 -17:00

Chair of Review Committee: Dr. Thorsten Hollands, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany
Keynote Coordinator: Dr. Erwin Fischer, PreussenElektra, Germany

TitleSpeaker
09:00Keynote: Safe to the Last Day – A Challenge for OperatorsChristoph Heil, EnBW Kernkraft GmbH, Executive Director, Germany
09:30Keynote: Is Safety Culture Perceptible and Measurable?Uwe Stoll, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Scientific and Technical Director, Germany
10:00Break
10:30Keynote: Preserving and Ensuring Competence and MotivationDr. Frank Sommer, PreussenElektra GmbH, Head of CoC Operations, Germany
Chair: Dr. Thorsten Hollands, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany
11:00Digital Transformation in Nuclear Industry – Focus: Site ApplicationsDr. Jan Leilich, New NP, IBGM Product Management, Germany
11:30Save to the Last Day – How to Manage the Complexity in a Multi-Year End of Life ProcessProf. Dr. Rüdiger von Der Weth, Hochschule für Wirtschaft und Technik Dresden, Germany
12:00Lunch Break
13:00Loca Scenario-Related Zinc Borate Precipitation Studies at Lab ScaleDr. Ulrich Harm, Technische Universität Dresden (TUD), Germany
13:15Simulation of Asymmetric Severe Accidents Using the Code System AC2Liviusz Lovasz, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany
13:30Simulation of the Bundle Test QUENCH-07 with the Severe Accident Analysis Codes ASTEC V2.1 and AC^2 – ATHLET CDFlorian Gremme, Ruhr-Universität Bochum, Germany
13:45Sensitivity and Uncertainty Analysis of the MCCI Model Results in AC2/COCOSYS for the OECD-CCI3 ExperimentDr. Claus Spengler, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany
14:15Dry Filter Method DFM 2.0 – The Newest Generation of Filtered Containment Venting SystemDr. Peter Hausch, Caverion Deutschland GmbH, Business Unit Krantz, Germany
14:45Simulation of Droplet Re-Entrainment From Water PoolsTobias Jankowski, Ruhr-Universität Bochum, Germany
15:00Break
Chair: Dr. Jürgen Sydow, TÜV Nord EnSys GmbH & Co. KG, Germany
15:30TESPA-ROD Code Prediction of the Fuel Rod Behaviour During Long-Term StorageDr. Heinz-Günther Sonnenburg, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Germany
15:45Considerations for Multi Unit Effects in Probabilistic Risk AssessmentDr. Felix Philipp Sassen, Westinghouse Electric Germany GmbH, Germany
16:00Model-Based Vulnerability Analysis of Complex InfrastructuresMathias Lange, Hochschule Magdeburg-Stendal, Germany
16:153D Surface Radiation Dosimetry of a Nuclear-Chicago NH3 Neutron HowitzerAhmet Ilker Topuz, Istanbul Technical University, Nuclear Energy, Turkey
16:30End of Session

Subject to change.