Course detail

Nuclear Equipment and Safety

FSI-LJZAcad. year: 2016/2017

This subject in its first part deepens knowledge of students in the area of foundations of nuclear reactor calculation, partly from the physics of nuclear reactor core point of view, partly from the heat energy generation and removal from the nuclear reactor core point of view and partly from the hydrodynamics of nuclear reactor core point of view. Further the subject explains the conceptual solution of nuclear power plants with various types of reactors, further it deals with selected machine equipment of nuclear power plants and also it deals with variants of advanced nuclear reactors.
Second part of this subject is dedicated to the technical and nuclear safety and to the problems of nuclear fuel a nuclear wastes. Further it deepens knowledge of students in the area of nuclear spent fuel handling, storing and in the area of methods of its further utilization.

Language of instruction

Czech

Number of ECTS credits

Mode of study

Not applicable.

Guarantor

prof. Ing. Oldřich Matal, CSc.

Department

Energy Institute (EÚ)

Learning outcomes of the course unit

Students obtain profundities in the area of nuclear reactors calculation, area of nuclear power stations concepts with various types of reactors and in the area of new trends in nuclear equipment development. Students further obtain profundities in nuclear safety area and in the area of spent nuclear fuel, its repositoring and further utilization.

Prerequisites

Applied nuclear physics basis.
Diffusional and critical equations of nuclear reactor.
Nuclear power stations heat circuits basis.
Basic concepts in nuclear safety area.
Basic concepts in spent nuclear fuel treatment area.

Co-requisites

Not applicable.

Planned learning activities and teaching methods

The course is taught through lectures explaining the basic principles and theory of the discipline. Exercises are focused on practical topics presented in lectures.

Assesment methods and criteria linked to learning outcomes

Credit: Active seminars attendance. Complete individual exercises and calculations. Pass credit test.
Exam: Test of nuclear energetics principles knowledge, nuclear equipment knowledge, ensuring of nuclear safety knowledge.

Course curriculum

Not applicable.

Work placements

Not applicable.

Aims

The aim of this subject is to inform students about nuclear reactors calculation basis and new trends in their development. Very important aim is to inform students about nuclear and technical power stations safety questions and with individual views on nuclear spent fuel utilization.

Specification of controlled education, way of implementation and compensation for absences

Lecture attendance is not obligatory.
Credit attendance is obligatory and it will be checked. Maximum number of nonexcused absences are 2. In case of higher absence is the student obligated to do an individual work in accordance with teachers requirements.

Recommended optional programme components

Not applicable.

Prerequisites and corequisites

Not applicable.

Basic literature

Bečvář J. a kol.: Jaderné elektrárny. SNTL Praha, 1981.
Heřmanský, B.: Termomechanika jaderných reaktorů. Academia, 1986.
Horák, Z., Krupka, F., Fyzika. SNTL Praha, 1981.
Stacey, W., M. Nuclear Reactor Physics. Wiley-VCH. 2007

Recommended reading

Dubšek, F.: Jaderná energetika. PC-DIR Brno, 1994

Classification of course in study plans

  • Programme M2I-P Master's

    branch M-ENI , 2 year of study, winter semester, compulsory

Type of course unit

 

Lecture

39 hod., optionally

Teacher / Lecturer

Ing. Martin Lisý, Ph.D.

Syllabus

1. Reactor physical calculation and reactor critical equation in monogrup approach.
2. Neutrons flux distribution in cylindrical reator.
3. Transient heat generation in the reactor core, kynetics equation.
4. Heat transmfer from fuel to coolant, simplified cases of solving.
5. Core hydrodynamics, heat removal from core channels.
6. Conceptual solution of NPS with pressurized water reactor, particurarly VVER type.
7. Conceptual solution of NPS with boiling water reactor, particurarly VVER type.
8. Conceptual solution of NPS with fast breeder, sodium cooled reactor, steam generators.
9. Advanced nuclear power stations (AP 600, EPR 1600).
10. Technical and nuclear safety, probabilistic a deterministic approach to safety evaluation, defence in depth
concept, safety and operation indicators.
11. Nuclear fuel sources, radwastes and state charge.
12. Nuclear spent fuel and radwaste storages.
13. Nuclear fuel, fuel cycle, methods of nuclear spent fuel separation and reprocessing.

Exercise

13 hod., compulsory

Teacher / Lecturer

Ing. Martin Lisý, Ph.D.

Syllabus

1. Revision of nuclear power engineering basis.
2. Cross section: difinition, properties.
3. Calculation of the cross sections of various substances and compositions.
4. Physical calculations of the reactor.
5. Reator critical equation, core critical dimensions and composition calculations.
6. Comarison of cilindrical, spheric and cubic core.
7. Calculation of main parameters of various power plants.
8. Calculation of main parameters of various power plants.
9. Calculation of temperature profiles inside nuclear fuel and reactor core.
10. MCNP software.
11. Technical und nuclear safety. Safety and operational parameters.
12. Spent nuclear fuel, radioactive transmutations, radwaste disposal.
13. Credit test.