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Curricula and Syllabi of FNSPE CTU in Prague

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Aktualizace dat: 28.8.2019

česky

Bachelor degree programmeNuclear Engineering
Year 3
course code teacher ws ss ws cr. ss cr.

Compulsory courses

The Equations of Mathematical Physics01RMF Klika 4+2 z,zk - - 6 -
Course:The Equations of Mathematical Physics01RMFdoc. Ing. Klika Václav Ph.D.4+2 Z,ZK-6-
Abstract:The subject of this course is solving integral equations, theory of generalized functions, classification of partial differential equations, theory of integral transformations, and solution of partial differential equations (boundary value problem for eliptic PDE, mixed boundary problem for eliptic PDE).
Outline:1. Introduction to functional analysis - factor space, Hilbert space, scalar product, orthonormal basis, fourier series, orthogonal polynoms, hermite operators, operator spectrum and its properties, bounded operators, continuous operators, eliptic operators
2. Integral equations - integral operator and its properties, separable kernel of operator, sequential approximation method, iterated degenerate kernel method, Fredholm integral equations, Volterra integral equations.
3. Classification of partial differential equations - definitions, types of PDE, transformations of partial differential equations into normal form, classification of PDE, equations of mathematical physics.
4. Theory of generalized functions - test functions, generalized functions, elementary operations in distributions, generalized functions with positive support, tensor product and convolution, temepered distributions.
5. Theory of integral transformations - classical and generalized Fourier transformation, classical and generalized Laplace transform, applications.
6. Solving differential equations - fundamental solution of operators, solutions of problems of mathematical physics.
7. Boundary value problem for eliptic partial differential equation.
8. Mixed boundary problem for eliptic partial differential equation.
Outline (exercises):1. Hilbert space
2. Linear operators on Hilbert spaces
3. Integral equations
4. Partial differential equations
5. Theory of generalized functions
6. Laplace transform
7. Fourier transform
8. Fundamental solution of operators
9. Equations of mathematical physics
10. Eliptic differential equations
11. Mixed boundary problem
Goals:Get acquainted with theory of generalized functions and its application to solving partial differential equations including mixed boundary problem.
Requirements:Basic course of Calculus, Linear Algebra and selected topics in mathematical analysis (in the extent of the courses 01MA1, 01MAA2-4, 01LA1, 01LAA2, 01VYMA held at the FNSPE
CTU in Prague).
Key words:Mathematical methods in physics, distributions, integral transfomations, partial differential equations
ReferencesKey References:
P. Stovícek: Methods of Mathematical Physics : Theory of generalized functions, CVUT, Praha, 2004. (in czech),
P. Stovícek: Methods of Mathematical Physics II: Theory of generalized functions II. Integral equations, elliptic operators, CVUT, Praha, 2017. (in czech),
V.S. Vladimirov : Equations of Mathematical Physics, Marcel Dekker, New York, 1971
Č. Burdík, O. Navrátil : Rovnice matematické fyziky, Česká technika - nakladatelství ČVUT, 2008

Recommended literature:
L. Schwartz - Mathematics for the Physical Sciences, Dover Publication, 2008
I. M. Gel'fand, G. E. Shilov, Generalized Functions. Volume I: Properties and Operations, Birkhäuser Boston, 2004

Numerical Methods 201NME2 Beneš - - 2+0 kz - 2
Course:Numerical Methods 201NME2prof. Dr. Ing. Beneš Michal-2+0 KZ-2
Abstract:The course is devoted to numerical solution of boundary-value problems and intial-boundary-value problems for ordinary and partial differential equations. It explains methods converting boundary-value problems to initial-value problems and finite-difference methods for elliptic, parabolic and first-order hyperbolic partial differential equations.
Outline:I.Numerical solution of ordinary differential equations - boundary-value problems
1.Shooting method
2Method of transformation of a boundary-value problem
3.Method of finite differences
4.Solution of non-linear equations
II.Numerical solution of partial differential equations of the elliptic type
1.Finite-difference method for linear second-order equations
2.Convergence and the error estimate
3.Method of lines
III.Numerical solution of partial differential equations of the parabolic type
1.Method of finite differences for one-dimensional problems
2.Method of finite differences for higher-dimensional problems
3.Method of lines
IV.Numerical solution of hyperbolic conservation laws
1.Formulation and properties of hyperbolic conservation laws
2.Simplest finite-difference methods
Outline (exercises):
Goals:Knowledge:
Numerical methods based on transformation of a boundary-value problem to an initial-value problem, finite-difference method for ODE's and PDE's.

Skills:
Application of given methods in particular examples in physics and engineering including computer implementation and error assessment.
Requirements:Basic course of Calculus, Linear Algebra and Ordinary Differential Equations (in the extent of the courses 01MA1, 01MAB2-4, 01LA1, 01LAB2, 12NMET held at the FNSPE CTU in Prague).
Key words:Boundary-value problems and initial-boundary-value problems for differential equations, shooting methods, finite-difference methods, energy methods giving properties of numerical schemes, explicit and implicit methods, conservation laws.
ReferencesKey references:
[1] A.A. Samarskij, Theory of Difference Schemes, CRC Press, New York, 2001
[2] J.W. Thomas, Numerical Partial Differential Equations: Finite Difference Methods, Springer Science & Business Media, 2013
[3] R.J. LeVeque, Finite Difference Methods for Ordinary and Partial Differential Equations, Steady State and Time Dependent Problems, SIAM, 2007
[4] R.J. LeVeque, Finite Volume Methods for Hyperbolic Problems, Cambridge University Press, 2002

Recommended references:
[5] E. Godlewski a P.-A. Raviart, Numerical approximation of hyperbolic systems of conversation laws, New York, Springer 1996

Media and tools:
Computer training room with Windows/Linux and programming languages C, Pascal, Fortran.

Nuclear Physics02ZJF Wagner 3+2 z,zk - - 6 -
Course:Nuclear Physics02ZJFRNDr. Wagner Vladimír CSc.3+2 Z,ZK-6-
Abstract:This scientific field presents formidable challenges both experimentally and theoretically, simply because we are dealing with the submicroscopic domain, where much of our classical intuition regarding the behaviour of objects fails us. The lecture is a basic introduction to very interesting regions of subatomic physics.
Outline:1.Introduction - basic definitions and historical review
2.Collision kinematics
3.Cross section properties
4.Basic features of atomic nuclei and nuclear forces
5.Nuclear models
6.Radioactive decay of nuclei
7.Experimental techniques of nuclear and particle physics
8.Nuclear reactions
9.Nuclear matter, its study and features
10.Particles and their interactions
11.Unified theories of matter and interactions
12.Applications of nuclear and particle physics, nuclear astrophysics
Outline (exercises):Testing knowledge on particular problems from chapters:
1.Introduction - basic definitions and historical review
2.Collision kinematics
3.Cross section properties
4.Basic features of atomic nuclei and nuclear forces
5.Nuclear models
6.Radioactive decay of nuclei
7.Experimental techniques of nuclear and particle physics
8.Nuclear reactions
9.Nuclear matter, its study and features
10.Particles and their interactions
11.Unified theories of matter and interactions
12.Applications of nuclear and particle physics, nuclear astrophysics
Goals:Knowledge:
Fundamentals of nuclear and subnuclear physics, laws of microworld, understanding of experimental methods at subatomic physics.

Skills:
Basic understanding and calculations in nuclear and subnuclear physics
Requirements:Basic course of physics. Knowledge from classical mechanics, theory of relativity, electricity and magnetisms as well as thermodynamics.
Key words:Radioactivity, nuclear decay, nuclear reactions, elementary particles, quarks
ReferencesKey references:
[1] W.S.C. Williams : Nuclear and Particle Physics, Oxford Science Publications, 2001
[2] B. Povh, K. Rith, Ch. Scholz, F. Zetsche: Particles and Nuclei. An Introduction to the Physical Concepts, Springer 2004

Recommended references:
[3] Ashok Das, Thomas Ferbel: Introduction to Nuclear and Particle Physics, John Wiley and Sons, 1994
[4] P.E.Hodgson, E Gadioli and E.Gadioli Erba: Introductory Nuclear Physics, Oxford Science Publications, 1997
[5] A. Beiser: Concepts of Modern Physics, McGraw-Hill Companies Date Published, 1995

Media and tools:
Lecture room with dataprojector

Quantum Physics02KF Jizba, Šnobl 2+1 z,zk - - 3 -
Course:Quantum Physics02KFIng. Mgr. Jizba Petr Ph.D.2+1 Z,ZK-3-
Abstract:State description, wave function, postulates of quantum mechanics, Born´s statistical interpretation, expectation values, Schrödinger equation, Heisenberg uncertainty principle, quantization of angular momentum, solution of simple systems, hydrogen atom.

Outline:1.Experiments leading to the formulation of QM
2.De Broglie's conjecture, Schroedinger's equation
3.Description of states and observables in QM
4.Harmonic oscilator
5.Quantization of angular momentum
6.Particle in spherically symmetric potential. Coulomb field.
7.Mean values of observables and transition probabilities
8.Time evolution of states
9.Particle in the electromagnetic field. Spin
10.Many particle systems, bosons and fermions
11.Quantum tunneling
Outline (exercises):Deepening the knowledge by explicit solution of problems related to

1. Schroedinger's equation
2. Description of states and observables in QM
3. Harmonic oscilator
4. Quantization of angular momentum
5. Particle in spherically symmetric potential. Coulomb field.
6. Mean values of observables and transition probabilities
7. Time evolution of states
8. Particle in the electromagnetic field. Spin
9. Many particle systems, bosons and fermions
11. Quantum tunneling
Goals:knowledge:
essential notions and structures of quantum mechanics, description of simple quantum systems

abilities:
computation of expectation values of observables and of time evolution
Requirements:Knowledge of linear algebra, probability theory, theoretical physics and calculus is expected.
Key words:Quantum mechanics, Dirac formalism, harmonic oscillator, multiparticle systems, hydrogen atom
ReferencesKey references:
[1] J. Formánek, Úvod do kvantové teorie, I.+II. díl, (Academie, Praha, 2004)
[2] D.J. Griffiths, Introduction to Quantum Mechanics, (Cambridge University Press, Cambridge, 2016)

Recommended references:
[3] A.Messiah, Quantum Mechanics, Two Volumes Bound as One, (Dover Publications, New York, 1999)
[4] J.J.Sakurai and J.J.Napolitano,
Modern Quantum Mechanics, Modern Quantum Mechanics, (Pearsony, Harlow, 2013)
[5] P.V. Landshoff, A. Metherell, W. G. Rees, Essential Quantum Physics, Cambridge University Press, Cambridge, 2010)

Experimental Neutron Physics17ENF Rataj - - 2+1 kz - 2
Course:Experimental Neutron Physics17ENFIng. Rataj Jan Ph.D.-2+1 KZ-2
Abstract:The lectures are mainly focused on detailed characterisation of neutron properties, characteristics of neutron (reactor and non reactor) sources, properties of prompt and delayed neutrons, neutron detection methods, neutron induced nuclear reactions, modification and adjustment of neutron field, science and industry neutron applications. Last lecture deals with experimental data processing and analysis.
The lectures are supplemented with experimental practices in the field of neutron detection, determination of delayed neutron properties, study of neutron diffusion in various materials, preparation and characterisation of photo-neutron source and neutron source calibration.
Experimental practices will be running at training reactor VR-1 and in the neutron laboratory.
Outline:1. Discovery of the neutron and its properties
Range: 1 lecture,
Topic of lecture: Discovery of the neutron and history of experimental neutron physics, the properties of the neutron and their experimental research (neutron mass, neutron lifetime and decay, neutron energy and wavelength, neutron charge, neutron spin and magnetic moment)

2. Neutron sources and their properties
Range: 1 lecture
Topic of lecture: Reactor and non reactor neutron sources. Types and characterisation of nuclear research reactors as a neutron source. Characterisation and properties (intensity and energy range) of non reactor neutron sources. Overview and description of radionuclide sources. Radionuclide sources calibration. Neutron generators. System of accelerator an target as a neutron source.

3. Prompt and delayed neutrons
Range: 1 lecture
Topic of lecture: Origin of prompt neutrons and their properties. Origin and importance of delayed neutrons. The properties of delayed neutrons. Experimental determination of delayed neutron properties. Delayed neutrons and its utilisation in experiments and research.

4. Neutron detection
Range: 1 lecture
Topic of lecture: General principles in particle detection. Possibilities and methods of neutron detection. Proton-recoil methods. Methods based on neutron-nuclear reactions. Overview and properties of neutron detectors (ionisation chamber, semiconductor detectors, scintillation detectors, thermoluminescent detectors). Neutron spectrometry.

5. Neutron-nuclear interactions
Range: 1 lecture
Topic of lecture: Overview and characterisation of neutron interactions with matter. Forces between neutrons and particles. Neutron-nuclear interactions. Neutron cross-sections. Elastic and inelastic scattering. Radiative capture. Fission. Neutron-nuclear interaction attended by nucleon emission.

6. Neutron fields adjustment
Range: 1 lecture
Topic of lecture: Modification of neutron spectra. Cold and ultra cold neutron sources. Modification of neutron beam profile and direction. Neutron collimators. Neutron channels and utilisation of neutron beams in experimental neutron physics.

7. Application and utilisation of neutrons
Range: 1 lecture
Topic of lecture: Overview of neutron applications in the field of industry, medicine, chemistry, biology, geology and archaeology. Representative experimental and industry application of neutrons. Neutron diffraction. Neutron radiography. Neutron activation analyses. Transmutation - silicon doping. Radioisotopes production for industry and medicine applications. Boron capture therapy.

8. Experimental data processing and analysis
Range: 1 lecture
Topic of lecture: Experimental data processing. Definition and separation of measurement errors and uncertainties. Mean value, variation and standard deviation. Error propagation, determination of errors from direct and indirect measurement values. Analysis, evaluation and presentation of experimental data.
Outline (exercises):Experimental practices will be running at training reactor VR-1 and in the neutron laboratory.

1. Neutron detection in VR-1 reactor core
Range: 1 practice
Topic of practice: Basic parameters and set up of neutron detection system. Determination of neutron detection system linearity and its nonlinearity correction. Measurement of neutron flux distribution in VR-1 reactor core by small gas filled detectors.

2. Delayed neutrons detection at VR-1 rector
Range: 1 practice
Topic of practice: Parameters of device for delayed neutrons detection at VR-1 rector. Detection of delayed neutrons emitted by irradiated fissionable material and determination of their basic properties. Determination of fissionable material mass using delayed neutron counting method.

3. Study of neutron diffusion
Range: 1 practice
Topic of practice: Study of neutron diffusion in graphite and water. Measurement of neutrons distribution emitted by neutron source in graphite prism and water bath. Determination of neutron diffusion length for graphite and water.

4. Study of photo-neutron source
Range: 1 practice
Topic of practice: Preparation of photo-neutron source at VR-1 reactor. Detection of neutrons produced by reaction of gamma ray with heavy water.

5. Neutron source calibration
Range: 1 practice
Topic of practice: Principle of manganese bath and its utilisation for radionuclide sources calibration. Neutron source (AmBe type) calibration in manganese bath. Determination of neutron source emission by manganese bath.

7. Seminar paper
Range: 1 practice
Topic of practice: Checking and evaluation of student reports from practices, presentation of experimental works and experimental results, discussion.
Goals:Knowledge: detailed knowledge of neutron properties and its interaction, knowledge of experimental methods using neutrons, comprehensive knowledge of industry and science neutron application
Ability: orientation in the given problems, application of gained knowledge in the fields of science, research and other experimental subject matter, ability of preparation and realisation of experimental works, processing of experimental values and its analysis and interpretation.
Requirements:17ZAF
Key words:neutron, experimental neutron physics, neutron sources, prompt and delayed neutrons, neutron interaction, neutron detectors, neutron detection
ReferencesKey references:
Paul Reuss: Neutron Physics, EDP Sciences, 2008, France, ISBN: 978-2-7598-0041-4
Liyuan Liang, Romano Rinaldi, Helmut Schober: Neutron Applications in Earth, Energy and Envirinmental Sciences, Springer Science+Business Media, LLC 2009, ISBN 978-0-387-09415-1
Matějka, K., et al.: Experimentální úlohy na školním reaktoru VR-1, skripta ČVUT, ČVUT, Praha 2005.

Recommended references:
Tatjana Jevremovic: Nuclear Principles in Engineering, Springer Science+Business Media, LLC 2009, ISBN 978-0-387-85607-0
International Atomic Energy Agency: The applications of research reactors, IAEA-TECDOC-1234, Vienna, 2001

Media and tools:
training reactor VR-1 and neutron laboratory at Department o nuclear reactors

Control Systems of Nuclear Reactors17BES Kropík - - 2+0 z,zk - 2
Course:Control Systems of Nuclear Reactors17BESdoc. Ing. Kropík Martin CSc.-2+0 Z,ZK-2
Abstract:Matter of the subject is concentrated on categorization of systems in nuclear power plant according to importance to nuclear safety; next on requirements of different categories of systems and typical instrumentation of research nuclear facilities and nuclear power plants. Attention is given to definition of nuclear safety, single failure criterion and redundancy, common cause failures, independence and diversity; furthermore to qualification of safety systems. At the end, lectures deal with control and safety systems of systems research nuclear facilities. The lectures are completed with visit of the training reactor VR 1 with demonstration of its safety and control system.
Outline:1. Nuclear safety and systems in nuclear facilities, introduction into problematic, introduction of lectures into complete education and relation to other subjects, objectives of the subject; definition of nuclear safety and its use in nuclear facilities, basic approaches to providing of nuclear safety

2. Categorization of systems in nuclear facilities according to IAEA 1; approach of IAEA to categorization of systems in nuclear facilities in accordance of their importance to nuclear safety, requirements on safety (protection) systems and safety related systems - e.g. control systems; defense in depth, single failure criterion, redundancy

3.Categorization of systems in nuclear facilities according to IAEA 1; independence, spatial separation and functional isolation of systems, common cause failures, diversity, control rooms, emergency control rooms, introduction into problematic of use of computers in systems important to nuclear safety

4. Categorization of system in nuclear power plants according to IEC, IEC612226 standard for categorization of systems in nuclear power plants, similarities and differences in comparison to IAEA; categories A, B, C, requirements on their structure, quality and reliability

5. Categorization of systems according to IEEE; American approach to categorization of system according to importance to nuclear safety, systems class 1E a non 1E, similarities and differences in comparison to IAEA and IEC

6. Requirements on protection systems according to German standards KTA; German requirements on protection systems of nuclear facilities according to KTA 3501, specific German requirements on reliability, functionality, diversity, backed-up power supply, signalization; comparison with common European and American standards

7. Requirements on instrumentation and control systems of nuclear power plants; architecture of systems, requirements on instrumentation, nuclear safety guarantee, life cycle of facilities, operation, documentation and licensing according to IEC61513

8. Qualification of systems; standard IEC60780 for qualification of systems, type test, operational experience, analysis; type tests methodology, documentation of operational experience, limitations of system qualification by analysis

9. Safety and control systems of research nuclear facilities; Safety Guide of Czech State Office for Nuclear Safety (SONS), requirements on safety and control systems of research nuclear facilities according to the Safety Guide of SONS, systems structure, redundancy, coincidence logic, diversity, backed-up power supply, signalization, reactivity control

10. Diagnostics of nuclear research facilities; neutron flux measurement - types of neutron chambers, pulse, DC current and Campbell regimes; technical realization, comparison of methods

11. Safety and control system of the VR 1 training reactor; system structure, its components and their importance, assessment of fulfillment of SONS Safety Guide requirements, safety limits, safety function, reactor operation

12. Excursion of VR 1 reactor; visit of safety and control system, human machine interface, system testing, reactor start up, reactor operation, neutron flux measurement, demonstration of safety functions

13. Instrumentation of other research nuclear facilities; instrumentation of LR 15 and LR 0 in NRI Ře6, training reactor in KURRI (Japan), SUR reactor in TU Dresden, reactor TRIGA MARK II in Atominstitut Vienna (Austria), reactor FRM in Garching (Germany) and reactor AGN in Suwon university (Republic of Korea)
Outline (exercises):No tutorials, only discussion about required literature and excursion at training reactor VR 1
Goals:Knowledge: detailed knowledge of safety systems of nuclear facilities, their philosophy, robustness against potential problems and failures

Abilities: orientation in matter of safety systems, use gained knowledge in other subjects of reactor physics, nuclear power plants and operator?s course during further education
Requirements:17ZAF
Key words:nuclear safety, safety systems of nuclear facilities, redundancy, diversity, single failure, common cause failure
ReferencesKey references:
Instrumentation and Control Systéme Important to Safety in Nuclear Power Plants, Safety Guide, NS-G-1.3, IAEA, Vienna, 2002

Recommended references:
Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions, IEC 61226, 2009
IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations -Description, IEEE Std 603-1998
Nuclear power plants - Electrical equipment of the safety system - Qualification, IEC60780, 1998

Media and tools:
training reactor VR 1 laboratory

Introduction to Radiation Protection of Nuclear Facilities17URO Starý - - 2+0 kz - 2
Course:Introduction to Radiation Protection of Nuclear Facilities17UROIng. Starý Radovan-2+0 KZ-2
Abstract:The course is focused on introduction to the problems of radiation protection at nuclear facilities; the legislative context; the utilization of radiation sources in controlled and monitored areas; practical activities to monitor and measure radiation situation, the protection of public and workers against ionizing radiation.
Outline:1.Radiation Protection
Scope: 1 lecture

Introduction, purpose and tasks of radiation protection and its relation to nuclear safeguards, physical protection and emergency preparedness. List of nuclear facilities in the Czech Republic and other countries. Literature review, study materials.

2. Radioactivity and ionizing radiation in the environment
Scope: 3 lectures

Radioactivity, the fundamentals and concepts, radioactive decay, the dose. Dose equivalent to evaluate the biological effects of ionizing radiation.

Effects of ionizing radiation on a human body. Artificial and natural sources of ionizing radiation. Radioactivity and the environment. Radioactive waste. The method of protection against adverse effects of radiation.

The radiation situation in the Czech Republic, releases of radioactivity from nuclear facilities during normal operation and accident conditions, analysis of selected accidents of various radiation sources.

3. Legislation in the field of radiation protection

Scope: 3 lectures

The Atomic Act from the perspective of radiation protection, SONS and its role, legislative conditions for the use of ionizing radiation.

Decree No. 307/2002 on radiation protection, the classification of sources of ionizing radiation, the exemption levels, categorizing workplaces, optimization and dose limits, the conditions of safe use of ionizing radiation and workplaces with them,

Continuous monitoring of radiation protection, controlled and monitored area; workplaces with radiation sources (enclosed, unsealed); the release of radionuclides into the environment, the release levels


4. Radiation monitoring

The purpose of the monitoring program and method of securing it. Monitoring of people, workplace monitoring, monitoring of discharges and environmental monitoring of nuclear facilities.

Instrumentation for ensuring the monitoring program. Dosimetric control equipment, calibration and measurement verification.

Measurements of dose rate of gamma rays and neutrons, measurement of surface contamination by alpha-beta radiation sources, a measurement of discharges. Monitoring of VR-1 reactor workplace.

Requirements for the Radiation Monitoring Systems, Radiation Monitoring System RMS VR-1 and the NPP Temelin. Early Warning Network of Czech republic, European monitoring network.


5. Working in a controlled and monitored area
Scope: 2 lectures

Topic of the lecture:
The method works with open and sealed sources, the quality assurance program in radiation protection. Manner and ensure safe working with ionization radiation for various nuclear facilities (reactor VR-1, NPP Temelin).

Activity in the exposure of people, contamination of the workplace and neighborhood. Internal and external emergency plan. Radiation emergencies and their solutions.

Outline (exercises):-
Goals:Knowledge: an overview of the requirements for radiation protection of nuclear facilities

Abilities: understanding the legislative context, the method of measurement, range monitoring to ensure
Requirements:-
Key words:radiological protection, nuclear devices, ionizing radiation, radiation sources, calibration, monitoring system
ReferencesKey references:
Hála J.: Radioactivity, ionizing radiation, nuclear energy, Konvoj Brno, 1998, (in Czech)
Act No. 18/1997 Coll. on Peaceful Utilisation of Nuclear Energy and Ionising Radiation (the Atomic Act), as amended

Recommended references:
Bodansky D.: Nuclear Energy: Principles, Practices, and Prospects, 2nd ed. editionRadiation Detection and Measurement, John Wiley & Sons, Inc., Springer-Verlag New York, 2004
International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (CD-ROM Edition, 2003)
Series No. 115/CD, IAEA, 2004

Media and tools:
Portable devices dosimetry Rados, RDS120, RDS200, Berthold LB122, Tesla NB3201. The monitoring system VR-1

Thermohydraulics Design of Nuclear Devices 317THNJ3 Kobylka, Heřmanský 2+1 z,zk - - 3 -
Course:Thermohydraulics Design of Nuclear Devices 317THNJ3prof. Ing. Heřmanský Bedřich CSc. / Ing. Kobylka Dušan Ph.D.2+1 Z,ZK-3-
Abstract:With this course, students are introduced into problem of thermohydraulic calculations. Step by step they will learn more about fundamentals chapters of heat transfer. Are discussed all types basic modes of heat transfer (conduction, convection a radiation). The lectures are focused to fields which are necessary for designs of nuclear reactors as well as others devices in nuclear power plants.
Outline:1. Introduction to heat transfer
Time range: 1 lecture
Basic modes of heat transfer (conduction, convection a radiation) and their short description, examples of application in nuclear devices, conjugate heat transfer, application of conservation of energy principle on checkplots.

10. Conduction
Time range: 5 lectures
Principles of conduction, Fourier law, thermal conductivity (mainly for material used in nuclear reactors, UO2), derivation of Fourier differential equation of heat transfer and their boundary conditions, solving of Fourier differential equation of heat transfer for simple cases of temperature fields and geometries: steady state conduction on wall (plane, cylindrical) without internal heat sources and with internal heat sources in the course of different boundary conditions, 1D conduction in fins and use of fin efficiency, fundamentals of 2D solution of conduction (plane wall, cylindrical wall with boundary condition as function of angle, ...), 1D transient heat transfer.

11. Convection
Time range: 5 lectures
Principles of convection, Newton equation and heat transfer coefficient, theory of similarity and field of its use, important dimensionless numbers and their derivation, determining quantities, single-phase external forced convection: plane wall (laminar, turbulent boundary layer, influence and rise of boundary layer, cross flow around pipe (laminar, turbulent, heat transfer coefficient as function of pipe perimeter), convection on tube bundle; single-phase external natural convection on walls in large space (vertical and horizontal plane walls), single-phase internal forced convection: issue of reference temperatures, inlet area, area of developed flow, laminar, turbulent flow; single-phase internal natural convection; two-phase convection: condensation (theory, film and drop condensation, determination of heat transfer coefficient on pipes and vertical walls), boiling (theory, nucleate boiling, film boiling, boiling crisis of 1st type, boiling crisis of 2nd type, critical heat flux, determination of heat transfer coefficient on pipes and vertical walls).

12. Fundamentals of heat radiation
Time range: 1 lecture
Principles of radiation, definition of quantities (emittance, emissivity, etc) and terms (black body, etc.), fundamental laws (Kirchhoff's law, Planck law, Wien law, Stefan-Boltzman law, etc.), radiation between parallel plates, radiation of general bodies, radiaton of gases.
Outline (exercises):Selected chapters are demonstrated on simple examples (heat transmission through wall, fins, temperature field in wall with internal heat source and unsymmetrical boundary conditions 3rd and 4th type, external convection (forced and natural), internal convection, boiling, radiation.
Goals:Knowledge: students will get basic knowledge about field of heat transfer, which they can use especially in solving of thermohydraulic of primary circuit and nuclear reactors core. This basic knowledge will allow them to get in detail designs of another devices of the nuclear power plants (for example heat exchangers, steam generators, condensators, etc.) and they will allow them to understand their operational and physical features.

Abilitiesi: Students will be better orientated in the given problematics and they will be able to work on basic simplified designs. Obtained knowledge will use in the following parts of this course (17THNJ4) and all consecutive course, which are focused on thermal and hydraulics problematic or designing of single devices in nuclear power plant. On base of given knowledge students will be able to understand and analyse behavior and control of nuclear power plant as a complex.
Requirements:THNJ1, THNJ2
Key words:heat transfer, Fourier law, heat equation, conduction, convection, radiation, thermal conductivity, theory of similarity, heat transfer coefficient, forced convection, natural convection, internal flow external flow, condensation, boiling, boiling crisis, critical heat flux
ReferencesMareš R., Šifner O., Kadrnožka J.: Tables of properties of water and steam somputed from the industrial formulation IAPWS-IF97, VUTIUM , 1999, ISBN 80-214-1316-6
Incropera, F. P., DeWitt D. P.: Introduction to Heat Transfer, John Willey & Sons, New York, 1996, ISBN 0-471-30458-1
Tong, L.S., Weisman, J.: Thermal Analysis of Pressurized Water Reactors, American Nuclear Society, Illinois USA, 1996, ISBN: 0-89448-038-3

Introduction to Nuclear Reactor Physics 217ZAF2 Frýbort, Frýbortová, Sklenka - - 2+1 z,zk - 3
Course:Introduction to Nuclear Reactor Physics 217ZAF2doc. Ing. Sklenka Ľubomír Ph.D.-2+1 Z,ZK-3
Abstract:Lectures follow up 17ZAF1 and expands application of diffusion theory derived based on Fick's low for diffusion in gases. Analysis of bare homogeneous reactor and homogeneous reactor with reflector is main part of lectures. Three basic geometry are considered in derivation - slab, sphere, cylinder.
Students learn to determine spatial distribution of neutron flux for each part (reactor core and reflector) and individual energetic groups, based on critical equation they learn how to calculate critical amount of fissile material or critical dimensions. Possible use of diffusion theory is discussed also for fast reactor and differences between thermal and fast reactors are stressed. Part is addicted to reactor regulation and analysis of control rods. There are also summarized differences between homogeneous and heterogeneous reactors.
Outline:1. Diffusion theory
9 lectures
Diffusion equation and boundary condition - neutron flux density, neutron current, Fick's low; diffusion equation of nuclear reactor - slab, sphere, cylinder; power peaking factor, critical equations - one group critical equation, two group critical equation for thermal reactors, modified one group critical equation; reactors with reflector - one group and two group analysis, time dependence diffusion equation; fast reactors, energy dependence of neutron flux

2. Kinetics and dynamics of nuclear reactors
1 lecture
Reactor kinetics - long term kinetics, fuel burn up, medium term and short term kinetics; point kinetics; reactor dynamics - temperature reactivity feedback (isotermic, moderator, void and Doppler coefficient of reactivity), influence of temeprature to multiplication factor, temperature dependence of diffusion parametres - diffusion coeficient, diffusion length, Fermi age

3. Slowing down of neutrons
1 lecture
Slowing down on hydrogen, slowing down in A>1 mater, spectrum of neutron source, slowing down in isotopes mixtures

4. Control rod
1 lecture
Influence of control rod; analysis of central absorption rod - evaluation of design, worth of rod, one group and two group calculation; eccentric rod; ring of control rods; control rod of fast reactor; reactor regulation

5. Heterogenous reactor
1 lecture
Quasi-homogeneous reactor, heterogeneous reactor - definition of individual coefficients and multiplication factor in heterogeneous reactor
Outline (exercises):Part of course are exercises. Based on study programs, there are six excercises (one per 14 days).
Expamples of different application of diffusion theory are solved. Calculations are focused on evalutation of neutron flux distribution in reacotr core or reflector and determination of critical size or critical composition.
Metodolgy of calculation is demonstrated also during lectures where the connection to the theory and aplicacion of assumption and boundary conditions is stressed.
Goals:Knowledge: deep knowledge of diffusion theory and its application for basic geometry of homogeneous reactor, calculation of reactor with reflector and understanding of difference between homogeneous and heterogeneous reactor

Abilities: good overview in problems, ability to criticize used goings and evaluate results with respect to standard neutron physical characteristics of reactor core

Requirements:pass 17ZAF1
Key words:diffusion theory, reactor core, reactor with reflector, critical equation, homogeneous reactor, heterogeneous reactor, control rods

ReferencesKey references:
1. John R. Lamarsh, Anthony J. Baratta, Introduction to Nuclear Engineering, Prentice FRÝBORT, Jan, Lenka HERALTOVÁ a Milan ŠTEFÁNIK. Úvod do reaktorové fyziky: teorie a cvičení. 1. vyd. V Praze: ČVUT, 2013. 120 s. ISBN 978-80-01-05322-5
2. LAMARSH, John R. Introduction to nuclear engineering. 3rd ed. Upper Saddle River: Prentice Hall, C2001. xv, 783 s. ISBN 0-201-82498-1.5
3. HEŘMANSKÝ, Bedřich. Jaderné reaktory. Praha: SNTL, 1981. 271 s
4. ZEMAN, Jaroslav. Reaktorová fyzika 1. Dotisk 2. přeprac. vyd. Praha: ČVUT, 2003. 203 s. ISBN 80-01-01933- 0
ZEMAN, Jaroslav. Reaktorová fyzika. 2. Vyd. 3. Praha: ČVUT, 2001. 147 s. ISBN 80-01-02337-0
Recommended references:
1. DOE Fundamentals Handbooks - Nuclear Physics and Reactor Theory, Vol. 1 a Vol. 2 , dostupné online
2. REUSS, Paul. Neutron physics. 1st ed. Les Ulis Cedex: EDP Sciences, 2008. xxvi, 669 s. ISBN 978-2-7598-0041-4

Basics of Electronics17ZEL Kropík 2+2 kz - - 3 -
Course:Basics of Electronics17ZELdoc. Ing. Kropík Martin CSc.2+2 KZ-3-
Abstract:Lectures provide basic information of electronics. In the beginning, lectures are devoted to passive components - resistors, capacitors, inductors and solution of electrical circuits with them. Next, lectures deal with semiconductor components (standard, Zener, capacitive, LED), bipolar, unipolar transistors and semiconductor components with more layers (thyristors and triacs). Lectures continue with general amplifiers and operational amplifiers. Finally, lectures deal with digital circuits, digital/analog and analog/digital converters. Lectures are completed with electronic laboratory exercises.
Outline:1. Basic phenomena and lows in electricity and magnetism, solution of electric circuits by Ohm and Kirchhoff laws
2. Resistors; their features and use, marking of resistors, varying resistors - potentiometers, trimming resistors, photoresistors, thermistors, etc, printed circuit boards and their use in electronics
3. Capacitors, inductors; features and use, charging and discharging of capacitor and inductors, capacitive and inductive reactance, inductors with iron and ferrite core
4. Solution of circuits with AC (alternating current) - analytical, complex-symbolic methods, Laplace transformation, effective value, Fourier trigonometric series and their use in electronics
5. Semiconductors, PN transistion, diods - standard, Zener, capacitive, PIN diodes, LEDs
6. Bipolar, unipolar transistors, thyristors, triacs, voltage and current power supplies, stabilizers - parallel, serial, switching
7. Amplifiers and operational amplifiers; basic features of amplifiers - amplification, frequency range, noise, distortion, phase characteristics, etc.; operational amplifiers, their features and basic use
8. Digital circuits 1, logical functions, data representation, review of technologies, combinational and sequential circuits
9. Digital circuits 2; digital circuits 74XXX series, examples of combinational and sequential circuits, programmable logical devices
10. Digital/analog and analog/digital converters, principles of function, resolution, accuracy, sample theorem, aplications
11. Training course with basic electronic equipment - multimeters, generators, osciloscopes, power supplies, counter, impedance meters, etc. Basic information about instruments, parameters setting and their checks, measurement of passive electronic components with different equipment
12. Training course focused on semiconductor components - V-A characteristics silicon and germanium diodes, Zener diodes, measurement of bipolar transistors characteristics, measurement of delay time of bipolar and unipolar transistors in linear and saturated regime
13. Measurement of operational amplifiers - amplification, signal range, frequency characteristics for different amplifications, slew rate, etc.

Outline (exercises):calculations of circuits complete lectures, electronic training courses (paragraphs 11., 12., 13.)
Goals:Knowledge: basic knowledge of passive and active electronic circuits, equipment for measurement and diagnostics in electronics

Abilities: apply gained knowledge in practice, be able to design and realize simple analog and digital electronic circuits
Requirements:02ELMA
Key words:electronics, analog and digital circuits, semiconductors, operational amplifiers, digital/analog and analog/digital converters
ReferencesKey references:
Prof. Dipl.-Ing. Herbert Frisch, Basic of electronics and elektronic circuits, SNTL, Praha 1987, (in Czech)

Recommended references:
Doc. Ing. Petr Hiršl, CSc., Basic of electronics, textbook ČVUT in Prague, 1989, (in Czech)

Media and tools:
electronic laboratory of Department of nucelar reactors for training course in electronics

Detection of radiation17DEZ Miglierini, Tichý 2+1 z,zk - - 3 -
Course:Detection of radiation17DEZprof. Ing. Miglierini Marcel DrSc. / Ing. Tichý Miloš CSc.2+1 Z,ZK-3-
Abstract:The course provides basic information on detection of ionizing radiation. Summary of basic knowledge of nuclear physics necessary to understand derived from parallel course 02ZJF is the content of the first lecture. The main part of the course contain information on sources of radiation and methods of radiation detection of neutrons. Spectroscopy is lectured similarly: all kinds of ionizing radiation with a special lecture on neutron spectroscopy. Emphasis is given on physical principles of detection and spectroscopy but appropriate detection technique and its set-up is provided in an appropriate detail. Last lecture as an introduction to laboratory exercises is devoted to theory of probability and mathematical statistics with emphasis on processing of experimental data because the course on theory of probability and mathematical statistics is no more in CV of nuclear engineering. Basics of writing of scientific article is provided also to make easier writing a laboratory protocol as first student scientific text. Laboratory exercise are rather important part of the course amounting about 2/3 of the time (5-6 tasks). Students are given a problem with prepared short description and task to measure some quantity(ies) and write a protocol as scientific text (an article). Exercise is carried out in groups of maximum 3 students; protocol is written individually.
Outline:1. Introduction + Basic principles of nuclear physics + Radioactivity
. structure of nuclei, binding energy, models of nucleus, unstable nuclei
. stability of nuclei, radioactive decay law, radioactive decay - types of decay
. decay chains
2. Sources of radiation
. types of ionizing radiation: characterization of the types of radiation
. classification of electromagnetic radiation
. basic notions: activity, intensity, flux, fluence, countrate, dose, sensitivity, resolution, etc.
. sources of ionizing radiation: radionuclides, nuclear reactor, accelerators
3. Interaction of radiation with matter:
. interaction of charged particles with matter, heavy and light charged particles
. interactions of photons with matter
. interactions of neutrons with matter (indicatively)
4. Detectors of ionizing radiation
. principles of detection
. gas-filled detectors: ionizing chambers (compensated and non-compensated), proportional counters, GM counters
. scintillator counters, scintillators, photo-multiplying tubes
. semiconducting detectors
. special detectors: TLD, Cerenkov counters, Wilson and bubble chamber, photoemulsion, superconducting counters, spark and corona detectors
5. Spectrometry of ionising radiation
. principles of spectrometry
. preamplifier, amplifier, shaping of pulses, single channel analyser, multichannel analyser
. coincidence and anticoincidence layout, active and passive methods of shielding
. modular systems of spectrometric chains
6. Detection of neutrons
. principles of detection of neutrons
. main types of detectors of neutrons according to the used reaction, detection material, timing and purpose and their characteristics
- gas detectors
- scintillators
- semiconducting detectors
- diamond detectors
- self-powered detectors
- thermoluminiscence detectors
- solid state track detectors
. dose rate meters, dosimeters for neutrons
. instrumentation of energetic reactor and reactor VR-1
7. Spectrometry of neutrons
. methods and experimental equipment
- integral and differential spectrometer
- TOF spectrometer
- Methods based on response from charged particles from detection reactions
- threshold reactions
- neutron diffraction
. unfolding of neutron spectra spectra
. examples of the results
8. Uncertainty and elaboration of experimental data
. uncertainty and error, classification of uncertainties
. accuracy and precision
. Probability theory
- basic definitions
. mathematical statistics
- point and interval estimates
- tests of hypotheses
. Direct and indirect measurement
- multidimensional random quantities
- correlated and non-correlated quantities
- processing of an indirect measurement, interpretation of the results
- uncertainty of an indirect measurement, propagation of uncertainties
. practical consequences
- rounding
- composition of graphs
- background correction
Outline (exercises):1. Task 1: Compton effect
2. Task 2: Determination of a working point (voltage) of a G-M detector and its utilization for determination of attenuation parameter of some materials
3. Task 3: Gamma spectrometry: efficiency and energy resolution of different types of detectors and energy calibration of a spectrometric chain and determination of an unknown source of radiation
4. Task 4: Range of alpha particles in the air (semiconducting detectors)
5. Task 5: Detectors of neutrons, basic setup and sensitivity
Goals:Knowledge: Thorough overview on the methods of detection for all types of radioactive radiation including the necessary topics of nuclear physics and basic principles of statistical elaboration of the results.
Abilities: To provide an overview on the topic, to design detection methods suitable both for research tasks and for practical application of radiation sources.
Requirements:
Key words:Detection of ionizing radiation, spectrometry, elaboration of experimental data, measurement of radioactivity
References1. Knoll, G. F.: Radiation_Detection_and_Measurement, John Wiley&Sons Inc., 2000,
2. Leo, William R., Techniques for Nuclear and Particle Physics Experiments, Springer-Verlag, Berlin, Heidelberg, 1987
3. Murray, Raymond LeRoy: Nuclear energy : An introduction to the concepts, systems, and applications of nuclear processes, Elsevier Inc., 2009
4. Leo, William R., Techniques for Nuclear and Particle Physics Experiments, Springer-Verlag, Berlin, Heidelberg, 1987


Engineering Mechanics14TM Kunz, Ondráček 2+2 z,zk - - 4 -
Course:Engineering Mechanics14TMprof. Ing. Kunz Jiří CSc.----
Abstract:The course represents a link-up between the theoretical mechanics of rigid bodies and engineering disciplines dealing with the stress and strain analysis of real structure parts.
Outline:1. Statics.
1.1 Elementary principles.1.2 Force equilibrium for bodies with various supports.1.3 Forces and moments transmitted by slender members.1.4 Truss girders.
2. Elastomechanics.
2.1 Stress. 2.2 Strain. 2.3 Mechanical properties. 2.4 Boundary conditions, supports and fixing of bars and beams 2.5 Axially loaded bars 2.6 Cylindrical Pressure Vessels 2.7 Stresses and deflections under flexural loading. 2.8 Statically determinate and indeterminate beams 2.9 Beam shearing stresses 2.10 Torsion of circular shaft 2.11 Elementary information about plane problems, plates, shells, notches and cracks, plastic deformations, strength of materials, creep and fatigue
Outline (exercises):1. Calculation of reactions.
2. Calculation of forces and moments transmitted by slender members.
3. Calculation of axial forces in truss girders.
4. Bar with fixed ends under axial loading. 5. Thin-walled presure vessel and pipe.
6. Simple beam - uniform and distributed load.
7. Fixed beem - uniform and distributed load.
8. Beam supported at one end and fixed at other, distributed load.


Goals:Knowledge: To obtain the basic knowledge about statics, elasticity and strength of materials with respect to standard engineering application.
Skills: To be able to calculate the reactions in supports of various kinds, forces and moments transmitted by slender members and axial forces in truss girders. To be able to assess deflections and stresses in these structural parts with simple loads and supports. Understanding of basic strength and lifetime problems.
Requirements:Physics - Mechanics.
Mathematical analysis.
Key words:Conditions of equilibrium, Reactions, Beams, Trusses, Shear force, Bending moment, Stress, Strain, Tension and compresion, Cyllindrical pressure vessel, Bending, Shear, Torsion, Strength of materials and structures.
ReferencesKey references:
[1] Kunz,J.: Technical Mechanics. Statics with Examples.Praha, Vydavatelství ČVUT 2014 (in Czech).
Oliva, V.: Technická mechanika - Elastomechanika.[Written materials for lectures P-KMAT-804/10]. Praha, ČVUT-FJFI-KMAT, 2010, 65 s.
Recommended references:
[1] Crandall,S.H. - Dahl,N.C. - Lardner,T.J.: An introduction to the mechanics of solids. Tokyo, McGraw-Hill Kogakusha 1972.
[2] Oliva, V.: Aplikovaná mechanika kontinua I - Elastomechanika. [University textbook FJFI]. ČVUT v Praze 1982.
[3]Sochor, M.: Strength of Materials. [University textbook FS]. Vydavatelství CVUT 2000.

Chemistry15CHB Drtinová, Silber - - 3+1 z,zk - 4
Course:Chemistry15CHBdoc. Ing. Silber Rostislav CSc.-3+1 Z,ZK-4
Abstract:At first, the principles of water treatment processes, the sources of radioactive contamination and the principles of the treatment of all types of wastes are discussed. The main attention is paid to the individual technological operations used to the purification of feeding waters and cooling circuit waters and of all liquid and gaseous radioactive media encountered in NPP. The technological operations used to the treatment of wastes and the corrosion problems of the construction materials are discussed in detail, too.
Outline:1. Mechanical processes for the treatment of waters (filtration, sedimentation, centrifugation). The principles of physical-chemical and chemical processes for the treatment of waters, sludge and gases (water clarification, ion exchange, evaporation, solidification of radioactive wastes, and the purification of gases).
2. Ion exchangers (structure, the basic types and properties, application for the water treatment, the types of apparatus and the realization of working cycle).
3. The radiochemical speciality of some operations of NPP (contamination of primary circuit water by fission and corrosion products and by the products of important radiochemical reactions).
4. The review of treatment processes used in NPP (the simplified technological diagrams).
5. The treatment of non-radioactive waters and sludge (supplementary and cooling water, condensate from secondary circuit, neutralization, dewatering of sludge, etc.).
6. The treatment processes of the primary circuit cooling water.
7. The purification of water from the storage pools with irradiated fuels.
8. The purification of sludge from steam generator.
9. The purification of the wastes from the ion exchanger?s regeneration and washing, of the leakage from primary circuit, etc.).
10. The purification and the storage of boric concentrate. The purification of radioactive gaseous wastes.
11. The treatment and deposition of radioactive wastes (liquid and solid wastes).
12. The problems of corrosion (the fundamentals of corrosion, the types of corrosion and the defence against the corrosion; the corrosion problems in primary and secondary circuits; experimental methods for the study of corrosion.
Outline (exercises):1. Summary of all data on the base of which the construction of flow sheet of non-active water treatment is possible (on the assumption that mechanical filtration, clarification and demineralization or deionization of water is considered).
2. The improvement of economy of the DEMI-water production - draw up the flow sheets.
3. Draw up the flow sheet of cooling tower water purification.
4. Draw up the flow sheet of so-called block purification of condensate (from second cooling circuit) on the assumption that radioactive contamination exists or not.
5. Draw up the flow sheets of purification of input water and of treatment of non-active wastes.
6. Draw up the flow sheets of decontamination of primary circuit cooling water (continuous decontamination and drain water decontamination).
7. Draw up the flow sheets of decontamination of water from the storage pools with irradiated fuels and the purification of sludge from steam generator.
8. Draw up the flow sheet of purification (decontamination) of radioactive gases including the treatment of corresponding wastes (there are the solid wastes in this case).
9. Draw up the flow sheet of purification of boric acid concentrate.
10. Draw up the flow sheet of the treatment of liquid radioactive wastes, including their solidification and deposition, resulting from evaporation procedure.
11. Draw up the complete technological flow sheet describing the mutual coupling of individual operations used in NPP to the purification of waters and waste disposal.
12. Credit work (the report accompanying the complete technological flow sheet mentioned above).
Goals:The postgraduates obtain the knowledge related to the physical and physico-chemical principles of water treatment, decontamination and corrosion processes, and of corresponding technological operations, including the treatment of wastes, used in NPP. The postgraduates obtain the competence to the evaluation and assessment of the influence of individual technological parameters on the purification and decontamination process and to the solution of operating failure.
Requirements:1. The basic knowledge of inorganic and physical chemistry.
2. The knowledge of nuclear chemistry bearing on uranium fission and on basic nuclear reactions.
Key words:filtration, sedimentation; centrifugation; water clarification; ion exchange;
contamination of waters of primary and secondary circuit; purification of waters
and sludges; purification of gaseous wastes; treatment of radioactive wastes;
deposition of radioactive wastes; corrosion

ReferencesKey references:
Kritsky V.G.: Water Chemistry and Corrosion of Nuclear Power Plant Structural Materials. American Nuclear Society, La Grange Park, Illinois, U.S.A., 1999.
Recommended references:
Water Chemistry of Nuclear Reactor Systems 8 (Proceedings, Vol. 1). British Nuclear Energy Society. Thomas Telford Ltd., London, 2000.

Bachelor Thesis 117BPJR12 Kobylka 0+5 z 0+10 z 5 10
Course:Bachelor Thesis 117BPJR1Ing. Kobylka Dušan Ph.D.0+5 Z-5-
Abstract:Subject deals with problematic of officially given theme of bachelor thesis and its defense during state examination that is necessary for completion of bachelor study. The guarantor of the given theme is an advisor that defines literature, checks the progress and ability of work defense, and operatively solves problems of the work. Student individually or with a little help of guarantor or consultant solves given problem. Theme of work is generally selected from the list and is approved by the head of department and the faculty dean. The work is evaluated by one opponent. Contact hours relate to cooperation with the supervisor and are solved according to work needs. The subject is therefore not included in the faculty timetable.
Outline:-
Outline (exercises):-
Goals:Knowledge: a particular field depending on a given project topic
Abilities: working unaided on a given task, understanding the problem, producing an original specialist text
Requirements:-
Key words:bachelor thesis
Referencesaccording to given bachelor thesis topic

Course:Bachelor Thesis 217BPJR2Ing. Kobylka Dušan Ph.D.-0+10 Z-10
Abstract:Subject deals with problematic of officially given theme of bachelor thesis and its defense during state examination that is necessary for completion of bachelor study. The guarantor of the given theme is an advisor that defines literature, checks the progress and ability of work defense, and operatively solves problems of the work. Student individually or with a little help of guarantor or consultant solves given problem. Theme of work is generally selected from the list and is approved by the head of department and the faculty dean. The work is evaluated by one opponent. Contact hours relate to cooperation with the supervisor and are solved according to work needs. The subject is therefore not included in the faculty timetable.
Outline:-
Outline (exercises):-
Goals:Knowledge: a particular field depending on a given project topic

Abilities: working unaided on a given task, understanding the problem, producing an original specialist text
Requirements:-
Key words:bachelor thesis
Referencesaccording to given bachelor thesis topic

Výuka jazyků04... KJ - - - - - -

Optional courses

Basics of Nuclear Safety17ZJBE Heřmanský, Heraltová, Kříž 4+0 zk - - 4 -
Course:Basics of Nuclear Safety17ZJBEIng. Frýbortová Lenka Ph.D. / prof. Ing. Heřmanský Bedřich CSc.4 ZK-4-
Abstract:Introduction: History and evolution of nuclear power plant safety. Classification of events, incidents, accidents, accident of US NPP TMI-2, accident of Chernobyl NPP. Basics of nuclear safety - legislative approach: safety principles of NPP, legislative frame of nuclear power plant safety, international requirements on NPP safety, defense-in-depth, safety culture, classification of NPP states and criteria of acceptance, safety analysis. Severe accidents of NPP with pressurized water reactors - engineering and physical approach: loss of coolant accident (LOCA), anticipated transient without scram (ATWS). Safety systems of modern NPP with pressurized water reactors: VVER, EPR, AP-1000.
The course consists of two parts: first is secured by prof. B. Heřmanský; the second one is secured by a group of external instructors from NRI and SONS coordinated by Z. Kříž (NRI). Instructors belong to notable experts in various fields of nuclear safety who works at least 30 years in the field, some of them have experience from international organizations- IAEA, NEA.
Outline:1. Introductory lecture
1 lecture
Issue of severe accidents with fuel meltdown. ALARA principle and issue of linearization of the radiation effects. Relationship of risks and costs in assuring safety. Evolution of safety philosophy.

2. Accident classification
1 lecture
Classification of incidents and accidents according to engineering and physical aspects. INES - International Nuclear Event Scale: seven levels, methods of incidents and accidents evaluation, examples of particular levels. List of initiating events for NPP accident analysis.

3. Accident of TMI-2 NPP
1 lecture
Babcock-Wilcox reactors, their design and safety systems. A brief outline of the accident evolution and its immediate causes. Analysis of the accident evolution after ten years: reconstructed course of events and actual damage to the reactor.

4. Accident of Chernobyl NPP
1 lecture
RBMK reactors, their design and safety systems. The course of the accident and its immediate causes. Corrective safety facilities. Sarcophagus construction and the current status. Consequences of the Chernobyl accident. Risks of further operation of the NPP with RBMK reactors.

5. Basics of nuclear safety (legislative approach)
2 lectures
Safety principles of nuclear power plants and the legislative framework for NPP safety. Atomic law, decree No. 195, European law and the use of nuclear energy. International requirements on projects of new nuclear power plants: IAEA Safety Standards Series, European Utility Requirements (EUR), WENRA association.

6. NPP defense-in-depth and safety culture
1 lecture
Defence-in-depth principle. Basic physical barriers, five levels of defense-in-depth, Safety culture: definition and nature, universal characteristics of safety culture, requirements on strategic level, safety culture indicators.

7. LOCA and severe accidents
2 lectures
Phenomenological description of LBLOCA, Serious NPP accident with fuel meltdown High- and low- pressure sequence of serious accident with fuel meltdown.

8. Safety systems of NPP
3 lectures
Safety systems of NPP with VVER reactors (440, 1000, III generation)
engineering and technological part, electrical part, I&C, construction part (containment). Safety systems of NPP with VVER of the III. generation EPR, AP-1000).

9. Nuclear safeguards
1 lecture
role of government, requirements on surveillance, main areas of evaluation activities, inspections, requirements, decisions, IAEA recommendations.

10. Approval process for nuclear facilities
1 lecture
Main stages of approval process

11. Probabilistic safety assessment (J. Dušek)
1 lecture
Deterministic/probabilistic assessment, PSA method

12. Nuclear fuel safty
1 lecture
Nuclear fuel requirements, acceptance criteria and their verification, higher enrichment and higher burn-up impact

13. Research for safety
1 lecture
National and international research programs, safety research need, research topics, experiences and benefits for Czech nuclear programme

14. Personel in nuclear facilities
1 lecture
Research and experience with NPP personnel, requirements on personnel, selected personnel, qualification verification of personnel - licenses

15. Principles for ensuring safety
2 lectures
Basic principles for ensuring the fuel and core safety, their practical applications, requirements on material, construction, degradation mechanisms and reducing of their impact

16. Radioactive wastes
1 lecture

17.Utilizing of operational experience
2 lectures
national and international experience exchange systems (IRS, WANO), practical example of NPP event analysis
Outline (exercises):-
Goals:Knowledge: Orientation in classification and evolution of events, incidents and accidents of NPP. Detailed knowledge of causes, evolution and consequences of the two largest NPP accidents (TMI, Chernobyl). Knowledge of nuclear safety basics. Overview of NPP safety systems and their resistance against potential incidents and accidents.

Abilities: Orientation in given issue, understanding of serious accident importance for nuclear power global safety. Overview of issues in assuring safety of gen. II (current NPPs) and gen. III (new nuclear source) NPPs.
Requirements:17ZAF, 17JARE
Key words:NPP safety, nuclear safety, safety systems of nuclear facilities, Chernobil NPP accident, TMI-2 accident, defense-in-depth safety culture, redundancy, diversity, single failure, common cause failure, acceptance criteria, safety analysis, accident analysis, serious accident, LOCA, ATWS, VVER, EPR, AP-1000, INES
ReferencesKey references:
Heřmanský B.: "Bezpečnost jaderných elektráren I., II., III., IV." Učební texty, 2009

Recommended references:
"Basic Safety Principles for NPP", Rev.1. INSAG-12 report, IAEAVienna 1999
"European Utlities Safety Requirements", Vol.1, Rev. C, state 5, April 2001
"Accident Analysis for Nuclear Power Plants", IAEA, Vienna, December 2002
Pernica R.: "Stav vývoje a přehled metod pro vyhodnocení neurčitosti" Výzkumná zpráva ÚJV-11798 T, říjen 2002

Reactor Experiments17REPR Rataj, Sklenka - - 2+2 kz - 5
Course:Reactor Experiments17REPRIng. Rataj Jan Ph.D. / doc. Ing. Sklenka Ľubomír Ph.D.2+2 KZ-5-
Abstract:The course is focused on experimental neutron and reactor physics. The first part of the course is focused on experimental neutron physics, namely characterisation of neutron properties, characteristics of neutron (reactor and non reactor) sources, properties of prompt and delayed neutrons, neutron detection methods, and neutron induced nuclear reactions. The second part of the course is focused on experimental reactor physics, namely experimental methods focused on reactivity measurement, determination of control rod characteristics in the nuclear reactor, dynamics study of nuclear reactor and critical experiment. Theoretical lectures are followed by experiments at Training reactor VR-1 and at Neutron laboratory, both operated by Department of nuclear reactors.
Outline:1. Research nuclear reactors
Duration: 1 lecture
Topic:
Experimental methods of nuclear reactor physics, classification of nuclear facilities and research reactors, classification, parameters and utilisation of research reactors in the field of experimental reactor physics

2. Experimental data processing and analysis
Duration: 1 lecture
Topic:
Experimental data processing, definition and separation of measurement errors and uncertainties, mean value, variation and standard deviation, error propagation, determination of errors from direct and indirect measurement values, analysis, evaluation and presentation of experimental data
3. Neutron sources and their properties, neutron sources
Duration: 2 lectures
Topics:
Discovery of the neutron and history of experimental neutron physics, the properties of the neutron and their experimental research (neutron mass, neutron lifetime and decay, neutron energy and wavelength, neutron charge, neutron spin and magnetic moment)

Reactor and non reactor neutron sources, types and characterisation of nuclear research reactors as a neutron source, characterisation and properties (intensity and energy range) of non reactor neutron sources, overview and description of radionuclide sources, radionuclide sources calibration, neutron generators, system of accelerator an target as a neutron source

4. Prompt and delayed neutrons
Duration: 1 lecture
Topic:
Origin of prompt neutrons and their properties, origin and importance of delayed neutrons, the properties of delayed neutrons, experimental determination of delayed neutron properties, delayed neutrons and its utilisation in experiments and research.

5. Neutron detection
Duration: 1 lecture
Topic:
General principles in particle detection, possibilities and methods of neutron detection, proton-recoil methods, methods based on neutron-nuclear reactions, overview and properties of neutron detectors (ionisation chamber, semiconductor detectors, scintillation detectors, thermo luminescent detectors), neutron spectrometry.

6. Neutron-nucleus interactions
Duration: 1 lecture
Topic:
Overview and characterisation of neutron interactions with matter, forces between neutrons and particles, neutron-nucleus interactions, neutron cross-sections, elastic and inelastic scattering, radiative capture, fission, neutron-nuclear interaction attended by nucleon emission.

7. Reactivity measurement in nuclear reactors
Duration: 1 lecture
Topic:
Static and dynamics techniques for reactivity determination, source multiplication method, Source-jerk method, Rod-drop method, positive period method, inverse kinetic method

8. Determination of control rod characteristics in the nuclear reactor
Duration: 1 lecture
Topic:
Integral and differential control rod worth, control rod worth, methods focused on determination of control rod characteristics: inverse rate method and source multiplication method, control rods inter-calibration
9. Approaching criticality, critical experiment
Duration: 2 lectures
Topics:
Legislative requirements of State office for nuclear safety for basic critical experiment realisation, basic requirements for core configurations in VR-1 reactor

Design of VR-1 reactor core configuration, neutron-physical characteristics of VR-1 reactor core and their determination
Outline (exercises):1. Neutron detection in VR-1 reactor core
Duration: 2 exercises
Topics:
Basic parameters and set up of neutron detection system, determination of neutron detection system linearity and its nonlinearity correction, measurement of neutron flux distribution in VR-1 reactor core by small gas filled detectors

2. Delayed neutrons detection at VR-1 rector
Duration: 2 exercises
Topics:
Parameters of device for delayed neutrons detection at VR-1 rector, detection of delayed neutrons emitted by irradiated fissionable material and determination of their basic properties, determination of fissionable material mass using delayed neutron counting method

3. Study of neutron diffusion
Duration: 2 exercises
Topics:
Study of neutron diffusion in graphite and water, measurement of neutrons distribution emitted by neutron source in graphite prism and water bath, determination of neutron diffusion length for graphite and water

4. Reactivity measurement at VR-1 reactor
Duration: 2 exercises
Topics:
Source-jerk, Rod-drop and positive period method application on reactivity measurement at VR-1 reactor

5. Control rod calibration at VR-1 reactor
Duration: 2 exercises
Topics:
Determination of control rod worth and its calibration curve in VR-1 reactor by inverse rate method and source multiplication method, control rods inter-calibration in VR-1 reactor

6. Approaching the critical state at VR-1 reactor
Duration: 2 exercises
Topics:
Prediction of unknown critical state at VR-1 reactor by inverse rate method, approaching the critical state at VR-1 reactor by gradual change of control rod position

7. Students' experiments? works evaluation
Duration: 1 lecture
Topic:
Students' experiments works, evaluation and discussion with the lecturer
Goals:An overview of neutron properties and its interaction, knowledge of experimental methods using neutrons, experimental reactor physics, knowledge and assumption of method focused on determination of basic neutron-physical and operational parameters in nuclear reactors
Application of acquired knowledge to solve problems, qualification and quantification of the effects of various physical quantities and phenomena on the operation of nuclear reactors and nuclear safety, ability of preparation and realisation of experimental works, processing of experimental values and its analysis and interpretation
Requirements:17ZAF, 17PSJR
Key words:Neutron, experimental neutron physics, neutron sources, prompt and delayed neutrons, neutron interaction, neutron detectors, neutron detection, experimental reactor physics, research reactor, reactivity measurement, control rods calibration, zero power reactor, critical experiment
ReferencesKey references:
Paul Reuss: Neutron Physics, EDP Sciences, 2008, France, ISBN: 978-2-7598-0041-4
Liyuan Liang, Romano Rinaldi, Helmut Schober: Neutron Applications in Earth, Energy and Envirinmental Sciences, Springer Science+Business Media, LLC 2009, ISBN 978-0-387-09415-1
Weston M. Stacey: Nuclear Reactor Physics, John Wiley & Sons, Inc., New York 2001, ISBN 0-471-39127-1

Recommended references:
Tatjana Jevremovic: Nuclear Principles in Engineering, Springer Science+Business Media, LLC 2009, ISBN 978-0-387-85607-0
Lewis E.,E.: Fundamentals of Nuclear Reactor Physics, Elsevier Inc., USA 2008, ISBN: 978-0-12-370631-7

Media and tools:
Training reactor VR-1 and Neutron laboratory at Department o nuclear reactors

Operator Course for Bachelors17OPKB Rataj, Kropík - - 4 z,zk - 4
Course:Operator Course for Bachelors17OPKBIng. Rataj Jan Ph.D.4 Z,ZK-4-
Abstract:The lectures are focused on reasearch end experimental nuclear reactors, their typical experimental equipments, fuel for research reactors, control and instrumentation systems of nuclear reactors and operation of research reactors. The main part of lectures deals VR-1 reactor and its operation and nuclear safety of research reactors.
The lectures are supplemented with practices at VR-1 reactor including practical acquaint oneself with VR-1 reactor, operation of VR-1 reactor technological systems, start-up and operation of VR-1 reactor and training of VR-1 reactor control and operation.
Outline:1. Research and experimental reactors
Range: 1 lecture,
Topic of lecture: Research and experimental reactors. Typical experimental equipments of research reactors. The research reactor fuels. Instrumentation and control systems of research reactors. Dosimetry and radiation monitoring systems of research reactors.

2. Training reactor VR-1 - its characterisation and structure
Range: 2 lectures,
Topic of lectures:
Reactor VR-1: detailed characterisation and description of its structure and description of instrumentations and equipments which are important for VR-1 reactor operation.
Experimental equipments of VR-1 reactor: complete overview and description of VR-1 reactor experimental equipments.

3. Training reactor VR-1 - operation and its management
Range: 3 lectures,
Topic of lectures:
Safety and operational documentation of VR-1 reactor: safety reports, limits and conditions, on-site emergency plan, operation rules and regulations.
Management of VR-1 reactor operation: the rules of shift operation, qualification and professional training, quality assurance system in reactor operation, operational inspections.
Safety operation of VR-1 reactor: assurance of nuclear safety, radiation protection, physical protection and emergency preparedness.

4. Safety of research nuclear facilities
Range: 2 lectures,
Topic of lectures:
Legal framework (acts and decrees) in Czech Republic, fundamentals of nuclear safety during commissioning and operation of nuclear facilities.
Fundamentals of quality assurance, emergency preparedness, radiation protection of nuclear facilities.
Outline (exercises):The practices will be running at training reactor VR-1.

1. Reactor VR-1
Range: 1 practice
Topic of practice: Practical acquaint oneself with VR-1 reactor, reactor vessels, fuel IRT-4M, control rods, neutron source, instrumentation and control system, water system, dosimetry systems, system of physical protection, auxiliary systems.

2. Operation of the reactor technological systems and manipulation at the VR-1 reactor
Range: 1 practice
Topic of practice: Operation and service of the reactor technological systems (water systems, air distribution system, electric components), manipulators used at the reactor, fuel handling, control rod handling and manipulation with experimental devices at VR-1 reactor.

3. Start-up of the VR-1 reactor
Range: 1 practice
Topic of practice: Practical acquaint oneself with human machine interface of VR-1 reactor, signalling system, safety signals, commands and messages of reactor control system, reactor operation modes, reactor set-up before its initialisation and start-up, start-up of the reactor.

4. Operation of the VR-1 reactor
Range: 1 practice
Topic of practice: Putting reactor into operation, manual and automatic operation, increasing and decreasing the power, various inspections and checks on the instrumentation and control system.
Goals:Knowledge: detailed knowledge of nuclear research facilities and nuclear safety, complete knowledge of VR-1 reactor and its components and devices, knowledge of operation documentation and operation management of VR-1 reactor.

Ability: orientation in the given problems, start-up and operation of VR-1 reactor.
Requirements:17ZAF1, 17PSJR, 17DEZ
Key words:nuclear research reactor, reactor control system, nuclear fuel, training reactor VR-1, nuclear safety, radiation protection, physical protection, emergency preparedness
ReferencesKey references:
Učební texty a soubory otázek pro přípravu a zkoušky vybraných pracovníků výzkumných jaderných zařízení - Sešit č. 3 Výzkumné a experimentální reaktory, SÚJB, Praha 2004

Učební texty a soubory otázek pro přípravu a zkoušky vybraných pracovníků výzkumných jaderných zařízení - Sešit č. 4 Technické popisy českých výzkumných reaktorů, SÚJB, Praha 2004

Učební texty a soubory otázek pro přípravu a zkoušky vybraných pracovníků výzkumných jaderných zařízení - Sešit č. 5 Bezpečnost a provoz výzkumných reaktorů, SÚJB, Praha 2004

Požadavky Státního úřadu pro jadernou bezpečnost na výzkumná jaderná zařízení pro zajištění jaderné bezpečnosti radiační ochrany, fyzické ochrany a havarijní připravenosti, bezpečnostní návod, SÚJB Praha, 2004

Recommended references:
Bezpečnostní zpráva školního reaktoru VR-1, ČVUT - FJFI, Praha 2007
Matějka, K., et al.: Experimentální úlohy na školním reaktoru VR-1, skripta ČVUT, ČVUT, Praha 2005.

Equipment Complex of Nuclear Power Plants 217TCJ2 Kobylka 3+0 zk - - 3 -
Course:Equipment Complex of Nuclear Power Plants 217TCJ2Ing. Kobylka Dušan Ph.D.-3+0 ZK-3
Abstract:The course familiarizes students with basic machine devices of nuclear power plants, which are important for their operation, as are: pressurizer system, pumps and blowers, steam and gas turbines, heat exchangers (condensers, steam generators, reheaters, feed water heaters, etc.) and pipes and valves. Informations about devices are given primarily in descriptive level. It means that students are familiarized with different designs, used materials, manufacturing and operational experiences and parameters of real devices from power plants. Students also receive basic outline of fundamental theory about calculations of devices.
Outline:1. Pressurizer Systems of Primary Circuit
1 lecture
The pressurizer function in the primary circuit, physical description of pressurizer, model and calculation of pressurizer, operational states of pressurizer, types of pressurizers and their construction, connection and construction of pressurizer subsystems (electrical heaters, letdown condenser, etc.).
2. Pumps
2 lectures
Pumps classification, operation principle and main features of miscellaneous pumps types, typical construction features of pumps, description of the most important pumps in nuclear power plant: primary circuit main recirculation pumps, feed pumps, condensate pumps, others pumps, pumps for liquid metals, components and a subsystems of pumps.

3. Steam turbines
2 lectures
Operation principle and basic construction, steam turbines classification, description of turbine construction, fundamental calculations, description of turbine components (seals, bearings, etc.), saturated steam turbines: unique features, humidity separation and reheating of steam, control of steam, turbines, detailed description of the 220 MW and 1000MW turbines.

4. Gas turbines and blowers for gas cooled reactors
1 lecture
Blowers operation principle, fundamental calculations, description of blower construction, basic features of blowers, gas turbines and their unique features, description of components and subsystems of gas turbines and blowers (seals, bearings, etc.).

5. Condensers systems and bypass valves
1 lecture
Condensers of steam turbines (thermal calculations, description, construction), cooling system of nuclear power plants (types of cooling, construction, cooling towers, etc.), bypass valves (their function and description).

6. Heat exchangers
1 lecture
Classification, construction, principle of thermal and hydraulic calculations, feed water regeneration systems, description of regenerative heat exchangers, construction of regenerative heat exchangers, deaerator.

7. Pipes and fittings in nuclear power plant
1 lecture
Standardization, classification, unique pipes in nuclear power plant, fitting types a description of typical fitting in nuclear power plant.

8. Steam generators
2 lectures
Position of steam generators in heat schemes of nuclear power plants, heat calculation of steam generator, steam generator of the VVER 440 a VVER 1000, vertical steam generators, steam generators in nuclear power plants with gas cooled and fast reactors, hydraulic calculation of steam generators.

9. Complete disposition of nuclear power plant
1 lecture
Bubble condenser, containments, air engineering, diesel-generators, layout of nuclear power plants and its parts.
Outline (exercises):
Goals:Knowledge: description and construction of the most important machine devices of nuclear power plant, fundamental calculations of selected machine devices of nuclear power plant.

Abilities: orientation in field of machine devices of nuclear power plant
Requirements:THNJ1, THNJ2, THNJ3
Key words:pressurizer, pump, steam turbine, blower, condenser, bypass valve, regenerative heat exchanger, deaerator, steam generator, bubble condenser, containment
ReferencesHejzlar R.: Stroje a zařízení jaderných elektráren, Díl 1, Nakladatelství ČVUT, Praha, 2000
Hejzlar R.: Stroje a zařízení jaderných elektráren, Díl 2, Nakladatelství ČVUT, Praha, 2000

Tong, L.S., Weisman, J.: Thermal Analysis of Pressurized Water Reactors, American Nuclear Society, Illinois USA, 1996, ISBN: 0-89448-038-3

Intership Bachelors17PRAXB Kropík 1 týden z - - 1 -
Course:Intership Bachelors17PRAXBdoc. Ing. Kropík Martin CSc.1 tyd Z-1-
Abstract:Inteship is intended for acquiring of deeper knowledge about systems and operation of nuclear power plant. At present, it takes part at nuclear power plant Dukovany or Temelín, where students in form of extended excursion make the acquaintance of all important parts of nuclear power plant and gain basic ideas about activities of reactor physicist and operator. Part of the intership is also visit of power plant training center and full-scope simulator.
Outline:Intership at nuclear powr plant proceeds according to plans prepared by nuclear power plant workers.

Example:
Monday: Organization questions
Tuesday: nuclear fuel: storage of fresh fuel, storage of spent fuel, manipulations
Wednesday: personal questions, accident management, nuclear safety
Thursday: power plant starup. full-scope simulator
Friday: emergency and accidents planning, nuclear power plant operation.


Outline (exercises):
Goals:Knowledge: detailed knowledge of individual systems and operation of nuclear power plant.

Abilities: orientation in problematic of nuclear power plant operation and its systems, handling with fuel elements.
Requirements:
Key words:nuclear power plant, primary circuit, secondary circuit, nuclear power plant operation, handling with fuel elements
References

Nuclear-Power-Plant Simulator Exercise17CSI Kobylka - - 0+3 z - 3
Course:Nuclear-Power-Plant Simulator Exercise17CSIIng. Kobylka Dušan Ph.D.0+3 Z-3-
Abstract:Course is pointed to pass to students the idea about main operating features of nuclear power plants with various types of reactors, about physical coupling amid single components of nuclear power plants and about principles of operating. In the theoretical part, there is briefly described each power plant and its simulator and simulator's physical background. The main part of this course is dedicated to practising of various tasks (rated output, transiensts, malfunction of components) on simulators. The course takes place in simulators of following power units: VVER-440, ABWR and CANDU 6. During these exercises the basic physical features of system are always analysed and there are also given reasons of their changes and connections between them.
Outline:1. Introduction to simulators
1 lecture
Simulator definition, simulator division according to approximation to reality, simulators importance in nuclear power, basic principles of simulators development, development environments for their development.

2. VVER-440 simulator
1 lecture, 5 exercises
Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks at primary circuit, leaks at secondary circuit, pumps failures, etc.).


3. ABWR simulator
1 lecture, 2 exercises
Description of ABWR system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks, pumps failures, etc.).

4. CANDU 6 simulator
1 lecture, 2 exercises
Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features.

5. General evaluation
1 exercise
General evaluation of systems and their characteristics, regulation modes and dynamic features.
Outline (exercises):1. Introduction to simulators
1 lecture
Simulator definition, simulator division according to approximation to reality, simulators importance in nuclear power, basic principles of simulators development, development environments for their development.

2. VVER-440 simulator
1 lecture, 5 exercises
Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks at primary circuit, leaks at secondary circuit, pumps failures, etc.).


3. ABWR simulator
1 lecture, 2 exercises
Description of ABWR system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks, pumps failures, etc.).

4. CANDU 6 simulator
1 lecture, 2 exercises
Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features.
Goals:Knowledge: detailed knowledge of simulated systems, basic operational states and characteristics of systems, control modes of nuclear power plants, physical couplings amid devices of power plant, dynamics of systems.

Abilities: judge dynamics behavior of nuclear power plant, orientation in devices on nuclear power plant and their functions.
Requirements:
Key words:simulator, operational states of nuclear power plant, VVER-440, ABWR, CANDU 6.
ReferencesKey references
Gieci A., Macko J.: Návody ke cvičením na SPVS+EDU, Provozní stavy, VÚJE, Trnava, 2007
Gieci A., Macko J.: Vedení výcviku na SPVS+ETE, Odborná studie, VÚJE, Trnava, 2004
IAEA: Boiling water reactor simulator, Workshop material, IAEA, Vienna, 2003, IAEA-TCS-23
Bereznai G.: Introduction to CANDU systems and operation, University of Ontario, Ontario 2003

Recommended references:
IAEA: Reactor Simulator Development, Workshop material, IAEA, Vienna, 2001, IAEA-TCS-12

Software Seminar 101SOS12 Čulík 0+2 z 0+2 z 2 2
Course:Software Seminar 101SOS1Ing. Čulík Zdeněk0+2 Z-2-
Abstract:Java, Java Beans,
Assembly language programming for microprocessors Intel 80x86
Outline:1. Introduction to Java programming language
2. Java Beans components
3. Assembly language programming for microprocessors Intel 80x86
4. Registers, memory addressing
5. Instruction set, instruction codes
6. Procedure call, numeric coprocessor, MMX instructions
7. Virtual memory (80386)
8. CISC and RISC processor architectures, 64-bit microprocessors
Outline (exercises):1. Simple application written in Java programming language
2. Java data types, comparison with other programming languages
3, Introduction to graphical user interface design using Swing library
4. Classes and methods
5. Arrays in Java, differences between implementations of arrays in Java, C and Pascal
5. Interfaces, data model for JList component
7. Trees and JTree graphical component
8. Dynamic type identification - reflection and introspection
9. File input and output
10. Registers and simple Intel 80x86 instructions
11. Debugging on machine instruction level
12. Subroutines and parameter passing conventions
13. Translation of some specific high level programming language construction to machine code
Goals:Knowledge:
Introduction to Java programming language.
Differences between Java and C++. Overview of Intel 80x86 microprocessor architecture.

Skills:
Development of simple Java Application.
Requirements:
Key words:Java, assembly language.
References[1] B.Eckel, Thinking in Java (4th Edition), Prentice Hall, 2006
[2] http://mindview.net/Books
[3] http://developer.intel.com

Course:Software Seminar 201SOS2Ing. Čulík Zdeněk-0+2 Z-2
Abstract:Graphical libraries GTK+ and Qt. Development of graphical user interface using C and C++ programming languages. Portable applications for Unix like operating systems, especially for Linux systems. Portability to Microsoft Windows.
Outline:1. Introduction to graphical user interface programming in Linux (GTK+ and Qt library)
2. Development of simple application for GTK library. Object oriented framework Qt
3. Basic user interface controls
4. Response to user events
5. Compilation of applications under Linus operating system.
Outline (exercises):1. Source code for simple GTK application
2. Compilation and linking
3. Programming callback routines as a response on user events
4. Designing user interface using Glage
5. Minimal application for Qt graphics library
6. Qt signals and slots
7. Using Qt Designer and Creator
8. Widgets for lists, tables and trees
9. KDE desktop environment and KDevelop application
Goals:Knowledge:
Structure of GTK and Qt graphical user interface libraries used in Unix based operating systems.

Skills:
Write a C or C++ application with graphical user interface for Linux operating system.
Requirements:
Key words:Qt, GTK, Linux.
References[1] J. Blanchette, M. Summerfield, C++ GUI Programming with Qt 4, 2nd Edition, Prentice Hall, 2008
[2] H. Pennington, GTK+ /Gnome Application Development, Sams, 1999
[3] M. Summerfield, Rapid GUI Programming with Python and Qt, Prentice Hall, 2007
[4] http://qt.nokia.com
[5] http://library.gnome.org/devel
[6] http://www.gtk.org

Introduction to Elementary Particle Physics02UFEC Bielčík 2+0 z - - 2 -
Course:Introduction to Elementary Particle Physics02UFECMgr. Bielčík Jaroslav Ph.D.2+0 Z-2-
Abstract:The course provides an easily accessible introduction to elementary particle physics. Development, methods, goals and perspectives of the subject are presented.
Outline:1. Basic notation in the field, elementary particles and properties, literature
2. Natural system of units, history of the field
3. Main kinematic definitions and relations
4. Cross section and it's calculation in classical physics
5. Sketch of the quantum theory structure, matrix elements and cross sections in quantum theory
6. Relativistic calibration quantum field theory, Feynmann diagrams, renormalization, calibration symmetry, Higgs mechanism
7. Standard model - quantum electrodynamics, Glashow-Weinberg-Salam theory of electroweak interactions, quantum chromodynamics
8. Quark model, hadron description using multiplets of SU(N)
9. Deep inelastic scattering of leptons on nucleons, parton model
10. Theory of elementary particles beyond standard model - Grand unification theory,super-symmetric theory, string theory
11. Passing of radiation through matter, experimental methods in elementary particle physics
12. Main types of detectors
13. ATLAS experiment - research program, description of the detector, structure of incoming data, analysis, obtained results
Outline (exercises):
Goals:Knowledge:
Insight into the elementary particle physics

Skills:
Orientation in the problematics of the elementary particle physics
Requirements:Knowledge of basic course of physics
Key words:Quantum mechanics, symmetries, elementary particles, quarks, leptons, Standard Model

ReferencesKey references:
[1] K. Nakamura et al.(Particle Data group), The Review of Particle Physics, J. Phys. G 37, 075021 (2010)

Recommended references:
[2] Martinus Veltman, Facts and Mysteries in Elementary Particle Physics,World Scientific 2003
[3] Martinus Veltman, Diagrammatica : The Path to Feynman Diagrams Press Syndicate of the University of Cambridge 1994 Transfered to digital printing 2001
[4] Walter Greiner, Berndt Mueller, Quantum Mechanics - Symmetries Springer-Verlag 2001

Basics of Economic Assessment17ZEH Starý 2+0 zk - - 2 -
Course:Basics of Economic Assessment17ZEHIng. Starý Radovan2+0 ZK-2-
Abstract:The course focuses on the economic evaluation of Nuclear power plants. Introductory lectures are concerned with an introduction to economy and the basic component parts of microeconomics. Lectures continued with insight into the business and managerial economics, explanation of the concepts of incomes, expenses, etc. and their applications in electrical energy resources evaluation. Second part of lectures is focused on evaluation of nuclear power plants - the fuel cycle and operations of NPP.
Outline:1. Introduction to Economics
Scope: 1 lecture
Lecture content:
Introductory lecture - introduction to the problems, explanation of basic terms. Economics and business administration, the basic concepts of microeconomics and macroeconomics.

2. Introduction to Microeconomics
Scope: 2 lectures
Lecture content:
Market and basic market elements, supply and demand, balance of economy, total,
average, fixed, variable and marginal costs and revenues, consumer behavior, theory of the firm, price formation, perfect and imperfect competition, examples of imperfect competition, monopoly, oligopoly, price and it´s regulation.

3. Introduction to Business Administration
Scope: 2 lectures
Lecture content:
Company's assets and capital structure, revenues, costs and profit of the enterprise, profit and relationships between the company's basic economic values, break-even point analysis, operating and financial leverage effect.

4. Economics of Electricity Production
Scope: 3 lectures
Lecture content:
Supply and demand for electricity, typical annual and daily consumption chart, fixed and variable costs of different power sources, construction of the supply function of electric energy and its shifts, examples according to selected market, capacity factors of different power sources

5. Externalities in power generation
Scope: 1 lecture
Lecture content:
The concept of externality, negative and positive externalities, externalities in energy, nuclear power externalities, comparisons between sources

6. Economics of nuclear energy,
Scope: 2 lectures
Lecture content:
Capital, O&M and fuel costs of nuclear power plants and their comparison with other sources, evaluation of nuclear fuel cycle - mining and milling, conversion, enrichment, fabrication, evaluation of fuel reprocessing and permanent storage, calculation of LCOE

7. Evaluating methods of investments
Scope: 2 lectures
Lecture content:
Marketing analyzes, weighted average cost of capital - corporate discount rates, static and dynamic methods of evaluating, PBP, NPT, IRR, examples

8. The theory of innovation
Scope: 1 lecture
Lecture content:
Innovative processes, Schumpeter innovation waves, innovation impulses, innovation lifecycle.
Outline (exercises):-
Goals:Knowledge:
Understanding the basic topics of microeconomics and business administration. Orientation in the differences between the evaluation of different sources of electricity. Understending of power market. Understanding the economic eveluation of fuel cycle and NPP operation.

Abilities:
Orientation in the given issue, understanding the economic differences in the production of el. energy from different sources.
Requirements:
Key words:Electricity, pool, exchange, supply, demand, market, consumption, production, costs, base load, peak load, price, fuel cycle
ReferencesSCHILLER, Bradley R. Mikroekonomie dnes. Brno : Computer Press, 2004. 412 s. ISBN 80-251-0169-X.
KIRSCHEN, Daniel S., STRBAC, Goran. Fundamentals of Power System Economics. 1st edition. Chichester England : John Wiley & Sons Ltd., 2004. 296 s. ISBN 0-470-84572-4.
STOFT, Steven. Power System Economics : Designing Markets for Electricity. 1st edition. [s.l.] : Wiley-IEEE Press, 2002. 496 s. ISBN 0-471-15040-1.

NORD POOL. Elspot Market Data [online]. Oslo, .

Research Reactors17VYR Sklenka 2+0 zk - - 2 -
Course:Research Reactors17VYRdoc. Ing. Sklenka Ľubomír Ph.D.-2 ZK-2
Abstract:Course is devoted to research reactors and their applications for the need of research and industry. Students get familiar with research reactor types and their experimental programme along with experimental equipment needed for particular applications and their specifics.
The course is supported by technical visit to research reactor workplace.
Outline:1. Introductory lecture
Scope: 1 lecture
introduction, research reactor in the world - overview, research reactor applications, specifics of research reactor operation, state supervision and research reactor, research reactors and IAEA documents, R&D - fundamental research, applied research, education and training, university education, lifelong learning

2. Research reactor types
Scope: 1 lecture
Research reactor types, research reactor applications - type of activities - active core / reactor component characteristics examination, reactor as a source of radiation (neutrons, gamma-rays, beta-rays, .); type of experiments - in-core and off-core experiments

3. Neutron activation analysis
Scope: 1 lecture
Neutron activation analysis - method principle, qualitative and quantitative NAA, NAA types - instrumental NAA (INNA), Cyclic instrumental NAA (CINNA), Epithermal instrumental NAA (EINNA), radiochemical NAA (RNNA), Pre-concentration NAA (PNNA), Derivative NAA (PNNA), prompt gamma NAA (PGNNA), delay gamma NAA (DGNNA), fields of NAA use, type of samples

4. Radioisotopes production
Scope: 1 lecture
Radioisotopes production - principle, applications in industry, medicine, agriculture, R&D

5. Neutron radiography
Scope: 1 lecture
Neutron radiography and tomography - principle, static radiography, motion radiography , real-time radiography, tomography,

6. Neutron capture therapy
Scope: 1 lecture
Neutron capture therapy (boron) - principle, applications

7. Material structure studies
Scope: 1 lecture
Material structure studies - concept of neutron scattering utilization (elastic and non-elastic), SANS method

8. Neutron transmutation
Scope: 1 lecture
silicon transmutation (doping), gemstone coloring, material irradiation- examination of material properties during ageing, principle of the method, practical applications, transmutation equipment design

9. Fuel and material testing
Scope: 1 lecture
Fuel and material testing - equipment development, testing and qualification. Fuel and material testing - ageing, corrosion, radiation effects, fuel and material qualification - temperature, pressure, radiation effects, development of new fuels and materials - fast reactors, high-temperature reactors, fusion, support of NPP operation - instrumentation tests, measurement methodologies

10. Nuclear data acquisition
Scope: 1 lecture
nuclear data - cross-section measurement, spallation reaction, fission yields, decay data, delayed neutrons

11. Other research reactor applications
Scope: 1 lecture
geochronology - samples dating, argon geochronology, fission track geochronology / U-Th geochronology, reactor as a source of positrons

12. Research reactor applications in praxis
Scope: 2 lectures
Technical visit of selected research reactor with emphasis on its utilization
Outline (exercises):
Goals:Knowledge: detailed knowledge of research reactor types and their potential use for research and industry.

Abilities: orientation in the matter, application of obtained knowledge in other courses in the field of construction and use of research reactors.
Requirements:-
Key words:nuclear reactor, research reactor, training reactor, research reactor applications, neutron activation analysis, radioisotope production, neutron radiography, neutron capture therapy, material structure examination, neutron transmutation, nuclear fuel and material testing, nuclear data acquisition, positron sources
ReferencesKey references:
Utilization Related Design Features of Research Reactors: A Compendium, Technical Report Series, IAEA-TSR-455, IAEA, Vienna, 2007

Recommended references:
The applications of research reactors, IAEA-TecDoc-1234, IAEA, Vienna, 2001

Physical Training 300TV34 ČVUT - z - z 1 1
Course:Physical Training 300TV3----
Abstract:
Outline:
Outline (exercises):
Goals:
Requirements:
Key words:
References

Course:Physical Training 400TV4----
Abstract:
Outline:
Outline (exercises):
Goals:
Requirements:
Key words:
References