Thermomechanics of Nuclear Fuels

The course is not on the list Without time-table
Code Completion Credits Range Language
17TERP Z,ZK 4 2P+2C Czech
Department of Nuclear Reactors

The course titled Thermomechanics of Nuclear Fuels introduces the fundamentals of fuel thermomechnics and fuel per-formance. The introductory lectures are devoted to various designs of nuclear fuels with an emphasis on light water reactors. The key parts of nuclear fuel cycle are reminded to students as well. Single components of nuclear fuels are then discussed and from fuel pellets over pellet-cladding gap to cladding and design of the assembly. Physical models related to thermal, mechanical and physical responses of nuclear fuels are presented including the effects related to the fuel burnup. After the introduction of particular models, interlinks and feedbacks are presented including the limitations on fuel design and nuclear safety. The design and construction of fuel assemblies is presented at the end with calcula-tions of their mechanical design. The theory will be further applied during exercises by using thermomechanical codes such as FRAPCON and FRAPTRAN.

Syllabus of lectures:

1.Nuclear fuel designs, thermomechanics of nuclear fuels

2.Fuels – thermophysical properties of nuclear fuel pellets

3.Cladding – properties of nuclear fuel cladding materials

4.Fuel pin – heat transfer in fuel-cladding gap, pellet-cladding interaction

5.Fuel assembly – mechanical design, construction

6.Description and behavior of fuel system performance during normal operation and AOO

7.Fuel system performance during accidental conditions, fuel safety criteria

8.Fuel performance and limitations during spent fuel storage, transport and disposal

Syllabus of tutorials:

FRAPCON code, its installation and structure are introduced first. Different simulation procedures are introduced and students will perform fundamental validation calculations using predefined input files. Later, they will utilize also FRAPTRAN code used for simulation of transient behavior of nuclear fuel pins. Both codes will be then coupled using SNAP tool and students will perform a complex simulation with nuclear fuel pin that is operated at stationary conditions followed by an accident. Students will also modify the source code by implementing new material correlations into both codes followed by a complex simulation of fuel performance.

Study Objective:
Study materials:

Key references:

[1]Motta A.T., Olander D.R., Wirth B.: Light Water Reactor Materials, American Nuclear Society, 2017

[2]Geelhood K., Luscher W.: FRAPCON-4.0 Integral Assessment, PNNL-19418 Vol, vol. 2, 2015

[3]OECD/NEA, Nuclear Science Comitee.: Nuclear Fuel Safety Criteria Technical Review - Second edition, NEA-7072, Paris, 2012

[4]Todreas N.E., Kazimi M.S.: Nuclear systems, volume I, CRC Press, 2012, ISBN 978-1-4398-0887-0

Recommended references:

[5]Bailly H., Ménessier D., Prunier C.: The Nuclear Fuel of Pressurized Water Reactors and Fast Reactors, Design and Behaviour, Lavoisier Publ. Inc., 1999

Further information:
No time-table has been prepared for this course
The course is a part of the following study plans:
Data valid to 2021-03-05
For updated information see http://bilakniha.cvut.cz/en/predmet6304206.html