Horst-Michael Prasser: Catalogue data in Autumn Semester 2012 |
| Name | Prof. em. Dr. Horst-Michael Prasser |
| Field | Kernenergiesysteme |
| prasser@lke.mavt.ethz.ch | |
| Department | Mechanical and Process Engineering |
| Relationship | Professor emeritus |
| Number | Title | ECTS | Hours | Lecturers | |
|---|---|---|---|---|---|
| 151-0123-00L | Experimental Methods for Engineers | 4 credits | 2V + 2U | T. Rösgen, R. S. Abhari, K. Boulouchos, M. Mazzotti, D. J. Norris, H.‑M. Prasser, P. Rudolf von Rohr, A. Steinfeld | |
| Abstract | The course presents an overview of measurement tasks in engineering applications. Different concepts for the acquisition, storage and processing of typical measurement quantities are introduced. Laboratory exercises from different application areas (especially in thermofluidics and process engineering) expand the theoretical foundations introduced in class. | ||||
| Learning objective | Introduction to questions of measurement techniques, with particular emphasis on thermo-fluids. Presentation of various classic sensor technologies and analytical procedures. Study of various applications in the laboratory. | ||||
| Content | Structure of measurement techniques - assignment Measurable dimensions: physical level (Electrical noise) Sampling, quantification, filtering Measurement of mechanical dimensions Measurement of thermodynamic dimensions Measuring in flows Measurement of process engineering process parameters. | ||||
| Literature | Holman, J.P. "Experimental Methods for Engineers", McGraw-Hill 2001, ISBN 0-07-366055-8 Eckelmann, H. "Einführung in die Strömungsmesstechnik", Teubner 1997, ISBN 3-519-02379-2 | ||||
| 151-0163-00L | Nuclear Energy Conversion | 4 credits | 2V + 1U | H.‑M. Prasser | |
| 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: http://www.lke.mavt.ethz.ch/education/material/NucEnConv | ||||
| Literature | Dieter Smidt: Reaktortechnik, Band 1 und Band 2, G. Braun Karlsruhe, 1971 | ||||
| Prerequisites / Notice | Course attendance confirmation condition: Pass of two written tests (multiple choice), participation in exercises | ||||
| 151-1053-00L | Thermo- and Fluid Dynamics  | 0 credits | 2K | L. Kleiser, R. S. Abhari, K. Boulouchos, P. Jenny, P. Koumoutsakos, C. Müller, H. G. Park, D. Poulikakos, H.‑M. Prasser, T. Rösgen, A. Steinfeld | |
| Abstract | Current advanced research activities in the areas of thermo- and fluid dynamics are presented and discussed, mostly by external speakers. | ||||
| Learning objective | Knowledge of advanced research in the areas of thermo- and fluid dynamics | ||||
| 151-2015-00L | Reactor Technology No enrolment to this course at ETH Zurich. Book the corresponding module directly at EPFL. | 4 credits | 3G | H.‑M. Prasser, external organisers | |
| Abstract | This course provides an overview of microfabrication processes used to produce micro-scale robots and will cover topics related to microactuators, microsensors, and modeling at these scales. The course will also investigate micromanipulation technologies, incl. the assembly of micron-sized parts, the manipulation of biological cells, and the types of robots used to perform these types of tasks. | ||||
| Learning objective | To comprehend (particularly in the context of light water reactors) the basic heat removal phenomena in a reactor core, identify the technological limits for heat generation from the viewpoints of fuel, cladding and coolant, and be introduced to optimization principles in reactor thermal design. | ||||
| 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 - Other types of reactors (overview) - Generation IV systems | ||||
| Literature | Distributed documents, recommended book chapters | ||||
| Prerequisites / Notice | Required prior knowledge: Neutronics Prerequisite for: Nuclear Safety (2nd sem.) | ||||
| 151-2035-00L | Radiobiology and Radiation Protection 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 | H.‑M. Prasser, R. Scheidegger, C. Wernli | |
| Abstract | The biological effect of primary and secondary ionizing radiation requires a limitation of exposure of persons working with radiation and radioactive substances in the frame of their professional activities, but also to the not directly involved public. This requires thorough monitoring of the doses and radiation protection measures, both limiting external and internal exposure. | ||||
| Learning objective | Deep understanding of the biological effect of ionizing, the nature of radiation fields, legal dose limits, methods of dosimetry and radiation protection | ||||
| Content | Physical basics, radioactivity, properties of sources of ionizing radiation, direct and indirect ionizing radiation (neutrons), interaction of radiation with matter, radiation transport, conversion from photon/particle flux to dose rate, shielding, dosimetric quantities and units, radiation detection, basic radiobiology, external dosimetry, environmental dosimetry, internal dosimetry, radon, regulatory framework (Regulations, justification, ALARA, safety culture), environmental and man-made radiation exposure, transport, waste and decommissioning, accidents and emergency issues, radio-ecology | ||||
| Lecture notes | Hand-outs will be distributed | ||||
| Literature | Frank H. Attix: "Introduction to Radiological Physics and Radiation Dosimetry" James E. Martin "Physics for Radiation Protection" Glenn F. Knoll "Radiation Detection and Measurement" | ||||
| Prerequisites / Notice | Prerequisites: Basic knowledge in atom and nuclear physics | ||||
| 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. | 3 credits | 2G | H.‑M. Prasser, J. Birchley, L. Fernandez Moguel, B. Jäckel, T. Lind | |
| 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 | ||||