Thermohydraulic Design of Nuclear Devices 3
Code  Completion  Credits  Range 

17THN3  Z,ZK  3  3+0 
 Garant předmětu:
 Lecturer:
 Tutor:
 Supervisor:
 Department of Nuclear Reactors
 Synopsis:

This course is set to improve the basic knowledge of students about problems of thermohydraulics. The students will learn more about specific modes of heat transfer (liquid metals, molten salts and gases), which can bee used for designs of GEN IV reactors, about flow of compressible fluids (gases, steam, ?.), twophase flow (important for emergency analyses of nuclear devices, description of power loaded parts of PWR or design of BWR) and subchannel analysis of fuel assemblies. It also includes extended commentary of turbulent flow and models, which were develop for its description. Students will also learn more about basic principles of CFD calculations and crags of their use.
 Requirements:

17THN1, 17THN2
 Syllabus of lectures:

1. Specific modes of conduction
Time range: 2 lectures
Convection in liquid metals: thermophysical properties of the most used liquid metals (sodium, solution of PbBi), differences of properties from normal coolants and their influence on calculations, forced and natural convection at internal flow in pipes or triangular channel in lattice of fast reactors and on plane wall. Convection in gases: thermophysical properties of the helium (coolant in VHTR), differences of properties from normal coolants and their influence on calculations, influence of high velocities, forced and natural convection at internal flow in pipes and on plane wall, principles of thermohydraulics design of layer with spherical fuel elements. Convection in molten salts: thermophysical properties of fluoride molten salts, their differences from normal coolants and dependence on solutions compositions, forced and natural convection at internal flow in pipes and on plane wall.
2. Compressible fluids flow
Time range: 1 lecture
Description principle of ideal gas flow, use of 1st thermodynamic law for open thermodynamic system, conversion of enthalpy to kinetic energy, flow through gap, sound velocity, Laval nozzle (principle and calculation), steadystate shock, steam flow (real gas).
3. Twophase flow
Time range: 4 lectures
Fundamentals of twophase flow and its miscellaneous patterns, diagrams of flow, principles of twophase flow description, definition of basic quantities and their calculation (void fraction, etc. ), twophase pressure drops, basic twophase flow modeling: single fluid models, two fluid model, four equation models, nonequilibrium models, sonic velocity and critical flow; flow instability: types of instability and their nature (flow pattern instability, Ledinegg instability, dynamic instability, thermal oscillation, etc.), analysis of selected instabilities; liquidvapor separation, ?.
4. Turbulent flow
Time range: 2 lectures
Description of turbulent flow, review of turbulent flow models and their principles, detailed descriptions and principles of turbulence models: Kepsilon, Komega, RNG, model with Reynolds stress, LES models, comparison of models.
5. Subchannel analysis
Time range: 1 lecture:
Principle of subchannel analysis and their use for fuel assemblies calculations, s transcription of basic flow equations for subchannel analysis, follow up equations fior subchannel analysis (turbulent mixing, pressure losses, etc.), application of subchannel analysis in computer codes and their list and features.
6. Primary circuit thermohydraulic
Time range: 1 lecture:
Hydraulic characteristic of primary circuits particular components: reactor, primary pipes, modes of main circulating pump, steam generator, primary circuit dynamic, flow in selected components of primary circuit (entrance, exit, etc.), vibration of selected components which is caused by flow.
7. CFD
Time range: 2 lectures
Principles of CFD, methods for transcription of differential equation of heat transfer and flow to differential form, detailed description of finite element method and finite volume method, short list of CFD codes and their description, problematic of interpretation of results CFD.
 Syllabus of tutorials:

Lectures are in selected chapters completed with calculations of practical examples: conduction in liquid metals, two phase flow, pressure drops in primary circuits, CFD calculation.
 Study Objective:

Knowledge: detailed knowledge of selected parts of fluid mechanics, thermodynamics and heat transfer (see list of lectures) which can be used in thermohydraulic designs generally or in specific design of primary circuit and others devices in nuclear power plants.
Abilities: orientation in given issue, use gained knowledge in other courses which are engaged in thermomechanics and designs of devices in nuclear power plants. 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:

Key references:
Tong, L.S., Weisman, J.: Thermal Analysis of Pressurized Water Reactors, American Nuclear Society, Illinois USA, 1996, ISBN: 0894480383
Star CD  User?s Guide and Tutorial, CD Adapco Group, 2001
Weseeling, P.: Principles of Computational Fluid Dynamics, Springer, 2000
Wilcox, D. C.: Turbulence modeling for CFD, DCW Industries, California, 2002
Tang Y.S., Coffield R.D., Markley R.A.: Thermal Analysis of Liquid Metal Fast Breeder Reactors, American Nuclear Society, Madison USA, 1978, ISBN: 0894480111
Recommended references:
Lahey R.T., Moody F.J.: The ThermalHydraulics of a Boiling Water Nuclear Reactors, American Nuclear Society, La Grange Park, 1993, ISBN 0894480375
McAdams W.H.: Heat Transmision, McGrawHill, 1954
Weseeling, P.: Principles of Computational Fluid Dynamics, Springer, 2000
Wilcox, D. C.: Turbulence modeling for CFD, DCW Industries, California, 2002
Media and tools:
PC classroom, CFD code StarCD
 Note:
 Further information:
 No timetable has been prepared for this course
 The course is a part of the following study plans: