361-0536/06 – 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 | Compulsory |
| Year | 1 | Semester | winter |
| | Study language | English |
| Year of introduction | 2010/2011 | Year of cancellation | 2022/2023 |
| 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
E-learning
Other requirements
Other demands for students are not requested
Prerequisities
Subject has no prerequisities.
Co-requisities
Subject has no co-requisities.
Subject syllabus:
1st Physical principles of nuclear energy,
2nd Radioactive decay, neutron nuclear reactions
3rd Balance of neutrons in a nuclear reactor. Fundamentals of dosimetry.
4th Physical calculation of nuclear reactor diffusion neutron
5th The critical equation of a nuclear reactor neutron flux.
6th The kinetics of nuclear fission. Operating and transient regimes.
7th Development and dissipation of heat in a nuclear reactor, the distribution of heat flow, temperature field in the course of the fuel element and core.
8th Operation and management of a nuclear reactor, the reactivity compensation, poisoning of the reactor, iodine pit zestruskování reactor dynamics in the supercritical state,
9th Compensation devices and power control. Compensation in the primary circuit coolant. Volume compensators. KO mathematical model, transition and operational processes. Thermal and hydraulic calculation KO VVER 440 and 1000
10th Basic types of nuclear power reactors, light-water, heavy water,
11th High, fast, and gas-cooled. Components of the nuclear reactor. Equipment for fueling.
12th Nuclear power plants. Nuclear energy cycle, fuel and fuel cell production, storage and disposal of nuclear waste.
13th Core of nuclear materials reaktorů.Aspects of nuclear reactor safety, nuclear safety.
14th Reactors with higher inherent and passive safety and III + IV.generace.
Thermonuclear reactors and power plants.
Conditions for subject completion
Occurrence in study plans
Occurrence in special blocks
Assessment of instruction