361-0536/07 – Nuclear Power Eguipment (JEZ)
Gurantor department | Department of Power Engineering | Credits | 4 |
Subject guarantor | prof. Ing. Stanislav Honus, Ph.D. | Subject version guarantor | prof. Ing. Stanislav Honus, Ph.D. |
Study level | undergraduate or graduate | Requirement | Choice-compulsory type A |
Year | 1 | Semester | winter |
| | Study language | Czech |
Year of introduction | 2019/2020 | Year of cancellation | |
Intended for the faculties | FS | Intended for study types | Follow-up Master |
Subject aims expressed by acquired skills and competences
Preparation of specialists in the field of thermal calculations, design and construction of nuclear power plant equipment. The course builds on mastered the material in "nuclear energy" in the BC study, termomechanics and heat and mass transfer. Students acquire detailed knowledge of the primary circuit of nuclear power plants, learn about the various components of different types of nuclear power facilities, allowing them to design and construction of the diploma work.
Teaching methods
Lectures
Seminars
Individual consultations
Project work
Summary
The subject deals with the area of thermal calculations, design and construction of nuclear power plants. The student will acquire more detailed knowledge of the primary circuit of the nuclear power plant, will be acquainted with individual components of various types of nuclear power equipment, enabling their design and construction.
Compulsory literature:
Recommended literature:
Additional study materials
Way of continuous check of knowledge in the course of semester
Credit test and oral exam.
E-learning
Other requirements
Another demands for student are not.
Prerequisities
Subject has no prerequisities.
Co-requisities
Subject has no co-requisities.
Subject syllabus:
1. Physical foundations of nuclear energy.
2. Radioactive transformations, neutron nuclear reactions.
3. Neutron balance in nuclear reactor. Basics of dosimetry.
4. Physical calculation of nuclear reactor, diffusion of neutrons.
5. Critical equation of nuclear reactor, neutron flux.
6. Kinetics of fission chain reaction. Operation and transition modes.
7. Development and dissipation of heat in nuclear reactor, distribution of heat flow, course of temperature field in fuel element and active zone.
8. Nuclear reactor operation and control, reactivity compensation, reactor poisoning, iodine pit, reactor shearing, supercritical dynamics,
9. Equipment for power compensation and regulation. Primary circuit coolant compensation. Volume compensators. Mathematical model of KO, transition and operational processes. Thermal and hydraulic calculation of KO VVER 440 and 1000.
10. Basic types of nuclear power reactors, light water, heavy water.
11. High temperature, fast and gas cooled. Nuclear reactor structural components. Fuel Exchange Equipment.
12. Operation of nuclear power plants. Nuclear energy cycle, fuels and fuel cells, nuclear waste production, storage and disposal.
13. Nuclear reactor core materials. Physical-technical aspects of nuclear reactor safety, nuclear safety.
14. Reactors with increased inherent and passive safety III + and IV generation. Thermonuclear reactors and power plants.
Conditions for subject completion
Occurrence in study plans
Occurrence in special blocks
Assessment of instruction