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Lecturer(s)
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Course content
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Content: - Survey current and advanced terms of primary loops of nuclear power plant. - Applied theory of heat generation and heat transmission in nuclear reactor. - Description of basic types of current and advanced nuclear reactors. - Description of conception of main designed units of primary loops of pressurized water reactors including active zone. - Survey of equipment necessary for service of reactor. - Transport equipment, exchange and storage of nuclear waste fuel. - Safety of nuclear power plant. 1. Primary loop equipment - introduction. Generation and transmission of heat in nuclear reactor. 2. Basic types of current energetic reactors 2.1. Pressurized water reactors 2.2. Boiling water reactors 2.3. Heavy water reactors 2.4. Gas cooled reactors 2.5. Fast reactors 2.6. Boiling channel reactors 2.7. Research and teaching reactors 3. Advanced reactor systems 3.1. Generation III+ 3.2. Generation IV 3.3. Reactors of small and moderated output 4. Main technologic units of primary loop of nuclear power plant 4.1. Nuclear reactors (PWR,VVER) 4.1.1. Pressurized containers of Nuclear Power Plant 4.1.2. Design of Nuclear Power Plant (BER) 4.1.3. Internal parts of Nuclear Power Plant 4.1.4. Fuel segments/modules 4.1.5. Steering rods 4.1.6 Actuating system of steering rods 4.2. Steam generators 4.3. HCČ 4.4. HCP 4.5. KO 4.6. Active and passive emergency systems 4.7. Mechanical equipment of reactor tower 4.8. Technological measurement in primary loop of Nuclear Power Plant 5. Reactor decommisioning, fuel exchange, transport, storage of nuclear fuel 6. Reliability of nuclear reactors 7. Safety of nuclear reactors 8. Service of equipment of primary loop of nuclear power plant
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Learning activities and teaching methods
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Lecture, Practicum
- Preparation for comprehensive test (10-40)
- 40 hours per semester
- Preparation for formative assessments (2-20)
- 16 hours per semester
- Preparation for an examination (30-60)
- 60 hours per semester
- Graduate study programme term essay (40-50)
- 40 hours per semester
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| prerequisite |
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| Knowledge |
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| describe the physical basis of the fission chain reaction |
| explain the principle of heat transfer in heat exchangers |
| use independently theoretical knowledge in the field of mechanics, electrical engineering, elasticity and strength, material science and machine parts |
| Skills |
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| propose the design of the pressure vessel and heat exchanger |
| use calculation programs to check the proposed design solutions |
| design appropriate materials and semi-finished products for various parts of power equipment |
| learning outcomes |
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| Knowledge |
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| comprehensively describe and explain the principle of operation of different types of nuclear reactors |
| describe the technical parameters, design solution and material composition of the basic parts of the primary circuit of nuclear power plants, especially the pressure vessels of nuclear reactors, internal parts, drives of regulatory authorities |
| comprehensively describe the design and material solution of fuel assemblies of nuclear reactors of various types |
| comprehensively describe and explain the function of passive and active emergency systems of nuclear power plants |
| describe and explain the function of auxiliary systems of nuclear power plants |
| Skills |
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| propose a design solution for individual parts of the primary circuit of nuclear power plants |
| design and assess systems of handling and transport of nuclear fuel at nuclear power plants |
| teaching methods |
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| Knowledge |
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| Lecture |
| Practicum |
| assessment methods |
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| Oral exam |
| Test |
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Recommended literature
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Alan E. Waltar, Donald R. Todd, Pavel V. Tsvetkov. Fast Spectrum Reactors. 2011. ISBN 978-1441995711.
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Bečvář, Josef. Jaderné elektrárny. Praha : SNTL, 1981.
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Bedřich Heřmanský. Termo-mechanika jaderných reaktorů. Academia, Praha, 1986.
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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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Lamarsh, John R.; Baratta, Anthony John. Introduction to nuclear engineering. 3rd ed. Upper Saddle River : Prentice Hall, 2001. ISBN 0-201-82498-1.
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