361-0536/03 – Nuclear Power Eguipment (JEZ)
| Gurantor department | Department of Power Engineering | Credits | 5 |
| 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 |
| Year | 1 | Semester | summer |
| | Study language | Czech |
| Year of introduction | 2013/2014 | Year of cancellation | 2020/2021 |
| 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:
Way of continuous check of knowledge in the course of semester
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 fundamentals of nuclear energy, radioactive decay, neutron nuclear reactions, balance neutrons in a nuclear reactor.
2. Physical calculation of nuclear reactor neutron diffusion, the critical equation of nuclear reactor neutron flux. Kinetics of fission chain reaction.
3. Operating and transients.
4. The development and heat in a nuclear reactor, the distribution of heat flow, process temperature field in the fuel element and the core.
5. Operation and control of the nuclear reactor compensation reactivity reactor poisoning, iodine pit, fluxing reactor.
6. Dynamics in the supercritical state, compensation devices and power control.
7. Compensation of coolant in the primary circuit, bubbler tank and insurance systems.
8. Transition and operational processes in the first circuit. Thermal and hydraulic design of nuclear reactors I. circuit MIR 1200, AP 1000 EPR.
9. Operation of nuclear power plants.
10. Thermal diagrams of nuclear power plants, thermal efficiency and ways of its improvement.
11. Nuclear energy cycle, fuel and fuel cell manufacturing, storage and disposal of nuclear waste. Incineration of radioactive waste. Radioactive management.
12. Materials reactor cores. Physico-technical aspects of nuclear reactor safety, nuclear security.
13. Passive and active safety systems. Classification of nuclear accidents.
14. Reactors with high inherent passive safety, and III + generation. Perspective types of nuclear power plants IV. generation.
Conditions for subject completion
Occurrence in study plans
Occurrence in special blocks
Assessment of instruction