Annalisa Manera: Catalogue data in Autumn Semester 2021 |
| Name | Prof. Dr. Annalisa Manera |
| Name variants | A. Manera |
| Field | Nuclear Safety and Multiphase Flows |
| Address | Nuclear Safety & Multiphase Flows ETH Zürich, ML K 13 Sonneggstrasse 3 8092 Zürich SWITZERLAND |
| Telephone | +41 44 633 87 76 |
| maneraa@ethz.ch | |
| Department | Mechanical and Process Engineering |
| Relationship | Full Professor |
| Number | Title | ECTS | Hours | Lecturers | |
|---|---|---|---|---|---|
| 151-0163-00L | Nuclear Energy Conversion Does not take place this semester. | 4 credits | 2V + 1U | A. Manera | |
| Abstract | Phyiscal fundamentals of the fission reaction and the sustainable chain reaction, thermal design, construction, function and operation of nuclear reactors and power plants, light water reactors and other reactor types, converion and breeding | ||||
| Learning objective | Students get an overview on energy conversion in nuclear power plants, on construction and function of the most important types of nuclear reactors with special emphasis to light water reactors. They obtain the mathematical/physical basis for quantitative assessments concerning most relevant aspects of design, dynamic behaviour as well as material and energy flows. | ||||
| Content | Nuclear physics of fission and chain reaction. Themodynamics of nuclear reactors. Design of the rector core. Introduction into the dynamic behaviour of nuclear reactors. Overview on types of nuclear reactors, difference between thermal reactors and fast breaders. Construction and operation of nuclear power plants with pressurized and boiling water reactors, role and function of the most important safety systems, special features of the energy conversion. Development tendencies of rector technology. | ||||
| Lecture notes | Hand-outs will be distributed. Additional literature and information on the website of the lab: 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 | ||||
| Literature | 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 credits | 3G | A. Manera, external organisers | |
| Abstract | 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. | ||||
| Learning objective | 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 | ||||
| Content | - 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 | ||||
| Literature | Distributed documents, recommended book chapters | ||||
| Prerequisites / Notice | 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 credits | 3G | A. Manera, T. Lind, D. Paladino | |
| Abstract | 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. | ||||
| Learning objective | 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). | ||||
| Content | 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. | ||||
| Lecture notes | Hand-outs will be distributed | ||||
| Prerequisites / Notice | 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 credits | 3G | A. Pautz, F. Leibundgut, A. Manera | |
| Abstract | 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. | ||||
| Learning objective | 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. | ||||
| Content | 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. | ||||
| Lecture notes | Slides will be handed out. | ||||
| Literature | 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 | ||||