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Course info
KKE / JEP
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Course description
Department/Unit / Abbreviation
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KKE
/
JEP
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Academic Year
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2023/2024
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Academic Year
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2023/2024
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Title
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Nuclear Power Plant Primary Circuit
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Form of course completion
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Exam
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Form of course completion
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Exam
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Accredited / Credits
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Yes,
6
Cred.
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Type of completion
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Oral
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Type of completion
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Oral
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Time requirements
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Lecture
4
[Hours/Week]
Tutorial
2
[Hours/Week]
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Course credit prior to examination
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Yes
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Course credit prior to examination
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Yes
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Automatic acceptance of credit before examination
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Yes in the case of a previous evaluation 4 nebo nic.
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Included in study average
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YES
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Language of instruction
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Czech
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Occ/max
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|
|
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Automatic acceptance of credit before examination
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Yes in the case of a previous evaluation 4 nebo nic.
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Summer semester
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4 / -
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0 / -
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2 / -
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Included in study average
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YES
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Winter semester
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0 / -
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0 / -
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0 / -
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Repeated registration
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NO
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Repeated registration
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NO
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Timetable
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Yes
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Semester taught
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Summer semester
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Semester taught
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Summer semester
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Minimum (B + C) students
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10
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Optional course |
Yes
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Optional course
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Yes
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Language of instruction
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Czech
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Internship duration
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0
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No. of hours of on-premise lessons |
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Evaluation scale |
1|2|3|4 |
Periodicity |
každý rok
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Evaluation scale for credit before examination |
S|N |
Periodicita upřesnění |
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Fundamental theoretical course |
No
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Fundamental course |
Yes
|
Fundamental theoretical course |
No
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Evaluation scale |
1|2|3|4 |
Evaluation scale for credit before examination |
S|N |
Substituted course
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None
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Preclusive courses
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N/A
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Prerequisite courses
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N/A
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Informally recommended courses
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N/A
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Courses depending on this Course
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N/A
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Histogram of students' grades over the years:
Graphic PNG
,
XLS
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Course objectives:
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Principle of nuclear reaction (fission, fusion). Principle of moderation. Nuclear fuel. Fuel rods structure. Control and emergency members structure. Passive and active emergency reactor systems. Reactor structure (internals, pressure vessels). Radiation heating. Heat transfer in nuclear reactor. Steam generator. Pressurized-water reactor. Boiling water reactor. Gas-cooled reactor. Metal-cooled reactor. Perspective reactor systems. Reactor shutdown, refuelling and spent nuclear fuel deposit. LOCA, nuclear events evaluation scale. Reliability of nuclear reactors. Nuclear reactor safety. Radioactivity and environment.
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Requirements on student
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Requests:
Credit: active participation in seminars, elaboration of reports, credit test.
Exam: complete knowledge of subject matter.Combined exam (written and oral), 60 min
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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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Activities
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Fields of study
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Guarantors and lecturers
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Literature
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Basic:
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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Basic:
Bečvář, Josef. Jaderné elektrárny. Praha : SNTL, 1981.
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Basic:
Dubšek, F. Základy teorie a stavby jaderných reaktorů. VUT Brno, 1990.
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Extending:
Alan E. Waltar, Donald R. Todd, Pavel V. Tsvetkov. Fast Spectrum Reactors. 2011. ISBN 978-1441995711.
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Extending:
IAEA NF-G-2.1 Quality and Reliability Aspects in Nuclear Power Reactor Fuel Engineering.
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Extending:
IAEA General Safety Requirements No. GSR Part 4 (Rev. 1) Safety Assessment for Facilities and Activities.
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Extending:
IAEA NP-T-2.10 Commissioning guidelines for nuclear power plants.
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Extending:
IAEA NS-G-2 Maintenance, Surveillance and In-service Inspection in Nuclear Power Plants.
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Extending:
IAEA SRS-82 (Rev 1) Ageing Management for Nuclear Power Plants: International Generic Ageing Lessons Learned.
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Extending:
IAEA TECDOC 1391 ? Status of advanced light water reactors.
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Extending:
IAEA-TECDOC-1590 Application of Reliability Centred Maintenance to Optimize Operation and Maintenance in Nuclear Power Plants.
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Extending:
IAEA-TECDOC-1789 Impacts of Electricity Market Reforms on the Choice of Nuclear and Other Generation Technologies.
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Extending:
IAEA-TECDOC-1791 CONSIDERATIONS ON THE APPLICATION OF THE IAEA SAFETY REQUIREMENTS FOR THE DESIGN OF NUCLEAR POWER PLANTS.
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Recommended:
IAEA NP-T-2.7 Project management in nuclear power plants construction: Guidelines and construcion 7.
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Recommended:
Heřmanský, Bedřich. Jaderné reaktory. Praha : SNTL, 1981.
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Recommended:
Rezepov, Denisov. Reaktory VVER-1000 dlja atomnych elektrostancij. Moskva, Akademkniga, 2004.
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Recommended:
Hejzlar, Radko. Stroje a zařízení jaderných elektráren - Díl 1. ČVUT Praha, 2000.
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Recommended:
Hejzlar, Radko. Stroje a zařízení jaderných elektráren - Díl 2. ČVUT Praha, 2000.
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Recommended:
Bedřich Heřmanský. Termo-mechanika jaderných reaktorů. Academia, Praha, 1986.
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On-line library catalogues
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Time requirements
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All forms of study
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Activities
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Time requirements for activity [h]
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Preparation for formative assessments (2-20)
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16
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Graduate study programme term essay (40-50)
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40
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Preparation for an examination (30-60)
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60
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Preparation for comprehensive test (10-40)
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40
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Total
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156
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Prerequisites
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Knowledge - students are expected to possess the following knowledge before the course commences to finish it successfully: |
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 - students are expected to possess the following skills before the course commences to finish it successfully: |
propose the design of the pressure vessel and heat exchanger
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use calculation programs to check the proposed design solutions
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design appropriate materials and semi-finished products for various parts of power equipment
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Learning outcomes
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Knowledge - knowledge resulting from the course: |
comprehensively describe and explain the principle of operation of different types of nuclear reactors
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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
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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
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describe and explain the function of auxiliary systems of nuclear power plants
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Skills - skills resulting from the course: |
propose a design solution for individual parts of the primary circuit of nuclear power plants
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design and assess systems of handling and transport of nuclear fuel at nuclear power plants
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Assessment methods
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Knowledge - knowledge achieved by taking this course are verified by the following means: |
Oral exam |
Test |
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Teaching methods
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Knowledge - the following training methods are used to achieve the required knowledge: |
Lecture |
Practicum |
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