Thermohydraulics Design of Nuclear Devices 3
Code  Completion  Credits  Range  Language 

17THNJ3  Z,ZK  3  2+1  Czech 
 Lecturer:
 Dušan Kobylka (guarantor)
 Tutor:
 Dušan Kobylka (guarantor)
 Supervisor:
 Department of Nuclear Reactors
 Synopsis:

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.
 Requirements:

THNJ1, THNJ2
 Syllabus of lectures:

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, singlephase 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; singlephase external natural convection on walls in large space (vertical and horizontal plane walls), singlephase internal forced convection: issue of reference temperatures, inlet area, area of developed flow, laminar, turbulent flow; singlephase internal natural convection; twophase 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, StefanBoltzman law, etc.), radiation between parallel plates, radiation of general bodies, radiaton of gases.
 Syllabus of tutorials:

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.
 Study Objective:

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.
 Study materials:

Mareš R., Šifner O., Kadrnožka J.: Tables of properties of water and steam somputed from the industrial formulation IAPWSIF97, VUTIUM , 1999, ISBN 8021413166
Incropera, F. P., DeWitt D. P.: Introduction to Heat Transfer, John Willey & Sons, New York, 1996, ISBN 0471304581
Tong, L.S., Weisman, J.: Thermal Analysis of Pressurized Water Reactors, American Nuclear Society, Illinois USA, 1996, ISBN: 0894480383
 Note:
 Timetable for winter semester 2020/2021:
 Timetable is not available yet
 Timetable for summer semester 2020/2021:
 Timetable is not available yet
 The course is a part of the following study plans:

 BS jaderné inženýrství B (compulsory course of the specialization)
 BS Jaderné inženýrství C (compulsory course of the specialization)