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Lecturer(s)
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Navara František, Ing. CSc.
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Kopecký Aleš, doc. RNDr. Ph.D.
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Havlík Jan, Ing. CSc.
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Course content
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Nuclear reactor as a subject of regulation. Basic therms from nuclear reactor regulation. Control and safety systems. Regulation of reactors - types: PWR, BWR, MAGNOX, AGR, CANDU, HTGR, FBR. Automatic regulation of a nuclear reactor. Complex design of regulation system. Regulation of power of nuclear reactor and complex nuclear power plant.
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Learning activities and teaching methods
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Lecture, Practicum
- Preparation for an examination (30-60)
- 60 hours per semester
- Preparation for comprehensive test (10-40)
- 40 hours per semester
- Preparation for formative assessments (2-20)
- 20 hours per semester
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| prerequisite |
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| Knowledge |
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| ability to describe and explain basic terms from the fields of nuclear physics and the theory of nuclear reactors |
| independent application of theoretical knowledge from the field of thermodynamics |
| to have an overview of neutron and radiation absorbent materials, their mechanical and physical properties, their corrosion resistances and their compatibility with other construction materials |
| Skills |
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| ability to read and understand technical documentation of a component or a simple assembly |
| understanding of graphs of basic physical and mathematical relationships |
| ability to read and understand varying types of systems schematics (e.g., regulatory, electrical, thermotechnical) |
| ability to solve simple tasks in the field of thermodynamics |
| physical and mathematical modeling of power systems machinery |
| Competences |
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| N/A |
| learning outcomes |
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| Knowledge |
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| knowledge of basic terminology from the field of nuclear power plant control systems |
| ability to describe and explain the scope and oddities of nuclear power plant control systems |
| ability to describe the structure of a typical nuclear block control system for different types of nuclear reactor |
| Skills |
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| ability to communicate with specialists in the fields of nuclear power plant measurements and nuclear power plant control systems |
| understand the choice of an appropriate type of measuring device or an active component in a nuclear block |
| ability to estimate behavior of a nuclear block in nonstandard situations |
| estimate the amount of heat produced and the intensity of radiation following the shutdown of a nuclear reactor |
| Competences |
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| N/A |
| teaching methods |
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| Knowledge |
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| Lecture |
| Lecture with visual aids |
| Skills |
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| Practicum |
| Field trip |
| Competences |
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| Lecture with visual aids |
| assessment methods |
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| Knowledge |
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| Oral exam |
| Skills |
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| Written exam |
| Competences |
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| Oral exam |
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Recommended literature
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Bečvář, Josef. Jaderné elektrárny. Praha : SNTL, 1981.
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Dubšek, F. Základy teorie a stavby jaderných reaktorů. VUT Brno, 1990.
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Hejzlar, Radko. Stroje a zařízení jaderných elektráren - Díl 1. ČVUT Praha, 2000.
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Hejzlar, Radko. Stroje a zařízení jaderných elektráren - Díl 2. ČVUT Praha, 2000.
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Heřmanský, Bedřich. Jaderné reaktory. Praha : SNTL, 1981.
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Tatjana Jevremovic. Nuclear Principles in Engineering. 2009. ISBN 978-0-387-85607-7.
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