Annalisa Manera: Katalogdaten im Herbstsemester 2022 |
| Name | Frau Prof. Dr. Annalisa Manera |
| Namensvarianten | A. Manera |
| Lehrgebiet | Nukleare Sicherheit und Mehrphasenströmungen |
| Adresse | Nuclear Safety & Multiphase Flows ETH Zürich, ML K 13 Sonneggstrasse 3 8092 Zürich SWITZERLAND |
| Telefon | +41 44 633 87 76 |
| maneraa@ethz.ch | |
| Departement | Maschinenbau und Verfahrenstechnik |
| Beziehung | Ordentliche Professorin |
| Nummer | Titel | ECTS | Umfang | Dozierende | |
|---|---|---|---|---|---|
| 151-0123-00L | Experimental Methods for Engineers | 4 KP | 2V + 2U | D. J. Norris, F. Coletti, M. Lukatskaya, A. Manera, G. Nagamine Gomez, B. Schuermans, O. Supponen, M. Tibbitt | |
| Kurzbeschreibung | The course presents an overview of measurement tasks in engineering environments. Different concepts for the acquisition and processing of typical measurement quantities are introduced. Following an initial in-class introduction, laboratory exercises from different application areas (especially in thermofluidics, energy, and process engineering) are attended by students in small groups. | ||||
| Lernziel | Introduction to various aspects of measurement techniques, with particular emphasis on thermo-fluidic, energy, and process-engineering applications. Understanding of various sensing technologies and analysis procedures. Exposure to typical experiments, diagnostics hardware, data acquisition, and processing. Study of applications in the laboratory. Fundamentals of scientific documentation and reporting. | ||||
| Inhalt | In-class introduction to representative measurement techniques in the research areas of the participating institutes (fluid dynamics, energy technology, process engineering) Student participation in 8-10 laboratory experiments (study groups of 3-5 students, dependent on the number of course participants and available experiments) Lab reports for all attended experiments have to be submitted by the study groups. A final exam evaluates the acquired knowledge individually. | ||||
| Skript | Presentations, handouts, and instructions are provided for each experiment. | ||||
| Literatur | Holman, J.P. "Experimental Methods for Engineers," McGraw-Hill 2001, ISBN 0-07-366055-8 Morris, A.S. & Langari, R. "Measurement and Instrumentation," Elsevier 2011, ISBN 0-12-381960-4 Eckelmann, H. "Einführung in die Strömungsmesstechnik," Teubner 1997, ISBN 3-519-02379-2 | ||||
| Voraussetzungen / Besonderes | Basic understanding in the following areas: - fluid mechanics, thermodynamics, heat and mass transfer - electrical engineering / electronics - numerical data analysis and processing (e.g. using MATLAB) | ||||
| 151-0163-00L | Nuclear Energy Conversion | 4 KP | 2V + 1U | A. Manera | |
| Kurzbeschreibung | Physikalische Grundlagen der Kernspaltung und der Kettenreaktion, thermische Auslegung, Aufbau, Funktion, und Betrieb von Kernreaktoren und Kernkraftwerken, Leichtwasserreaktoren und andere Reaktortypen, Konversion und Brüten | ||||
| Lernziel | Die Studierenden erhalten einen Überblick über die Energieerzeugung in Kernkraftwerken, über Aufbau und Funktion der wichtigsten Reaktortypen sowie über den Kernbrennstoffkreislauf mit Schwerpunkt auf Leichtwasserreaktoren. Sie erhalten die mathematisch-physikalischen Grundlagen für quantitave Abschätzungen zu den wichtigsten Aspekten der Auslegung, des dynamischen Verhaltens und der Stoff- und Energieströme. | ||||
| Inhalt | Neutronenphysikalische Grundlagen von Kernspaltung und Kettenreaktion. Thermodynamische Grundlagen von Kernreaktoren. Auslegung des Reaktorkerns. Einführung in das dynamische Verhalten von Kernreaktoren. Überblick über die wichtigsten Reaktortypen, Unterschied zwischen thermischen Reaktoren und Brutreaktoren. Aufbau und Betrieb von Kernkraftwerken mit Druck- und Siedewasserreaktoren, Rolle und Funktion der wichtigsten Sicherheitssysteme, Besonderheiten des Energieumwandlungsprozesses. Entwicklungstendenzen in der Reaktortechnik. | ||||
| Skript | Vorlesungsunterlagen werden verteilt. Vielfältiges Angebot an zusätzlicher Literatur und Informationen unter https://www.ethz.ch/content/specialinterest/mavt/energy-technology/lab-of-nuclear-energy-systems/en/studium/teaching-materials/151-0163-00l-nuclear-energy-conversion.html | ||||
| Literatur | S. Glasston & A. Sesonke: Nuclear Reactor Engineering, Reactor System Engineering, Ed. 4, Vol. 2., Springer-Science+Business Media, B.V. R. L. Murray: Nuclear Energy (Sixth Edition), An Introduction to the Concepts, Systems, and Applications of Nuclear Processes, Elsevier | ||||
| 151-2015-00L | Reactor Technology (EPFL) No enrolment to this course at ETH Zurich. Book the corresponding module directly at EPFL. | 4 KP | 3G | A. Manera, externe Veranstalter | |
| Kurzbeschreibung | Basic heat removal phenomena in a reactor core, limits for heat generation and technological consequences arising from fuel, cladding and coolant properties, main principles of reactor thermal design, as well as the general design of the nuclear power plant with its main and auxiliary systems are explained. The system technology of the most important thermal and fast reactor types is introduced. | ||||
| Lernziel | By the end of the course, the student must be able to: (1) Understand design principles of nuclear reactors, (2) Understand purpose and function of main reactor and power plant components and subsystems, (3) assess and evaluate the performance of reactor types, (4) systematize reactor system components, (5) formulate safety requirements for reactor systems | ||||
| Inhalt | - Fuel rod, LWR fuel elements - Temperature field in fuel rod - Reactor core, design - Flux and heat source distribution, cooling channel - Single-phase convective heat transfer, axial temperature profiles - Boiling crisis and DNB ratio - Pressurized water reactors, design - Primary circuit design - Steam generator heat transfer, steam generator types - Boiling water reactors - Reactor design - LWR power plant technology, main and auxiliary systems - Breeding and transmutation, purpose of generation IV systems - Properties of different coolants and technological consequences - Introduction into gas-cooled reactors, heavy water moderated reactors, sodium and led cooled fast reactors, molten salt reactors, accelerator driven systems | ||||
| Literatur | Distributed documents, recommended book chapters | ||||
| Voraussetzungen / Besonderes | Required prior knowledge: Neutronics Prerequisite for: Nuclear Safety (2nd sem.) | ||||
| 151-2039-00L | Beyond-Design-Basis Safety Students registered at ETH Zurich have to enroll to this course at ETH. EPFL students can enroll to this course directly at EPFL. | 4 KP | 3G | A. Manera, T. Lind, D. Paladino | |
| Kurzbeschreibung | Comprehensive knowledge is provided on the phenomena during a Beyond Design Bases Accident (BDBA) in a Nuclear Power Plants (NPP), on their modeling as well as on countermeasures taken against radioactive releases into the environment, both by Severe Accident Management Guidelines (SAMG), together with technical backfitting measures in existing plants and an extended design of new NPP. | ||||
| Lernziel | Deep understanding of the processes associated with core degradation and fuel melting in case of sustained lack of Core Cooling Systems, potential threats to the containment integrity, release and transport of active and inactive materials, the function of the containment, countermeasures mitigating release of radioactive material into the environment (accident management measures, back-fitting and extended design), assessment of timing and amounts of released radioactive material (source term). | ||||
| Inhalt | Physical basic understanding of severe accident phenomenology: loss of core cooling, core dryout, fuel heat-up, fuel rod cladding oxidation and hydrogen production, loss of core coolability and, fuel melting, melt relocation and melt accumulation in the lower plenum of the reactor pressure vessel (RPV), accident evolution at high and low reactor coolant system pressure , heat flux from the molten debris in the lower plenum and its distribution to the lower head, RPV failure and melt ejection, , direct containment heating, molten corium and concrete interaction, in- and ex-vessel molten fuel coolant interaction (steam explosions), hydrogen distribution in the containment, hydrogen risk (deflagration , transition to detonation), pressure buildup and containment vulnerability, countermeasures mitigating/avoiding hydrogen deflagration, formation, transport and deposition of radioactive aerosols, iodine behavior, plant ventilation-filtration systems, filtered venting to avoid containment failure and mitigate activity release into the environment, containment bypass scenarios, source term assessment, in-vessel and ex-vessel corium retention, behavior of fuel elements in the spent fuel pool during long-lasting station blackout, cladding oxidation in air, discussion of occurred severe accidents (Harrisburg, Chernobyl, Fukushima), internal and external emergency response. Probabilistic assessment and interfacing with severe accident phenomenology. | ||||
| Skript | Hand-outs will be distributed | ||||
| Voraussetzungen / Besonderes | Prerequisites: Recommended courses: 151-0156-00L Safety of Nuclear Power Plants plus either 151-0163-00L Nuclear Energy Conversion or 151-2015-00L Reactor Technology | ||||
| 151-2045-00L | Decommissioning of Nuclear Power Plants Students registered at ETH Zurich have to enroll to this course at ETH. EPFL students can enroll to this course directly at EPFL. | 4 KP | 3G | A. Manera, F. Leibundgut | |
| Kurzbeschreibung | Introduction to aspects of Nuclear Power Plant decommissioning including project planning and management, costs and financing, radiological characterization, dismantling/decontamination technologies, safety aspects and radioactive waste management considerations. | ||||
| Lernziel | Aim of this course is to provide the students with an overview of the multidisciplinary issues that have to be addressed for the successful decommissioning of NPPs. Students will get exposed to principles of project management, operations management, cost estimations, radiological characterization, technologies relevant to the safe dismantling of NPPs and best-practice in the context of radioactive waste management. | ||||
| Inhalt | Legal framework, project management and operations methods and tools, cost estimation approaches and methods, nuclear calculations and on-site radiological characterization and inventorying, state-of-the-art technologies for decontamination and dismantling, safety considerations, state-of-the-art practice for radioactive waste treatment, packaging and transport, interface with radioactive waste management and disposal. The course will additionally include student visits to relevant nuclear sites in Switzerland and Germany. | ||||
| Skript | Slides will be handed out. | ||||
| Literatur | 1. "Nuclear Decommissioning: Planning, Execution and International Experience", M. Laraia, Woodhead Publishing, 2012 2. "Cost Estimation: Methods and Tools", G.M. Mislick and D.A. Nussbaum, Wiley, 2015 3. "The Oxford Handbook of Megaproject Management", B. Flyvbjerg, Oxford University Press, 2017 | ||||