Vinh Dang: Katalogdaten im Frühjahrssemester 2016 |
Name | Herr Vinh Dang |
Adresse | Paul Scherrer Institut (PSI) OHSA / D16 5232 Villigen PSI SWITZERLAND |
Telefon | +41 56 3102967 |
dangv@ethz.ch | |
Departement | Maschinenbau und Verfahrenstechnik |
Beziehung | Dozent |
Nummer | Titel | ECTS | Umfang | Dozierende | |
---|---|---|---|---|---|
151-0156-00L | Safety of Nuclear Power Plants | 4 KP | 2V + 1U | H.‑M. Prasser, V. Dang, L. Podofillini | |
Kurzbeschreibung | Knowledge about safety concepts and requirements of nuclear power plants and their implementation in deterministic safety concepts and safety systems. Knowledge about behavior under accident conditions and about the methods of probabilistic risk analysis and how to handle results. Basics on health effects of ionizing radiation, radiation protection. Introduction of advanced nuclear systems. | ||||
Lernziel | Prepare students for a deep understanding of safety requirements, concepts and system of nuclear power plants, providing deterministic and probabilistic methods for safety analysis, equiping students with necessary knowledge in the field of nuclear safety recearch, nuclear power plant operation and regulatory activities. Learning about key elements of future nuclear systems. | ||||
Inhalt | Physical basics, functioning and safety properties of nuclear power plants, safety concepts and their implementation into system requirements and system design, design basis accident and severe accident scenarios and related physical phenomena, methods of probabilistic risk analysis (PRA level 1,2,3) as well as representation and assessment of results; lessons from experienced accidents, health effects of ionizing radiation, legal exposure limits, radiation protection; advanced active and passive safety systems, safety of innovative reactor concepts. | ||||
Skript | Hand-outs will be distributed | ||||
Literatur | Kröger, W., Chan, S.-L., Reflexions on Current and Future Nuclear Safety, atw 51 (2006), p.458-469 | ||||
Voraussetzungen / Besonderes | Prerequisites: Recommended in advance (not binding): 151-0163-00L Nuclear Energy Conversion and 151-0153-00L "Reliability of Technical Systems". |