Thermomechanical Design of Nuclear Fuels
- Department of Nuclear Reactors
The course title thermomechanical design of nuclear fuels directly follows the course 17TMECH. The fundamental knowledge introduced in the 17TMECH course are further elaborated towards particular subchapters of the safety reports of light water reactors (Chapter - Reactor) and design of nuclear fuels including advanced concepts. All of the components and their construction of nuclear fuel system are introduced (fuels, cladding, assemblies, control assemblies) together with their links to fundamental safety and operational functions of nuclear reactors. The safety/operational/limiting criteria used by US NRC and OECD/NEA will be discussed together with their origin and implications to nuclear reactor construction. Standard operational modes as well as transport, storage or disposal of nuclear fuels are included. These limitations will be practically studied by simulation codes Bison and FAST. New fuel designs and advanced fuel concepts will be presented at the end including Lightbridge fuel, double-cooled fuels, accident tolerant fuels together with current trends towards increasing enrichment and burnups.
- Syllabus of lectures:
1.Standard fuel systems of nuclear reactors
2.Design and fabrication of fuel pellets – geometrical limits, thermophysical limits according to the US NRC; nominal operation and limiting conditions
3.Design and construction of fuel cladding – alloys; limiting characteristics, safety criteria
4.Fuel pin – design (mechanical and thermal), material compatibility, radiation damage, PCMI and PCI limits
5.Fuel assembly – mechanical design of assemblies – bowing, debris, grids, stiffness.
6.Safety criteria and their evaluation using FAST and Bison codes.
7.Coupling of simulation tools – iterative approach to the design of nuclear fuel systems
8.New trends in the fuel system designs – advanced materials, burnable absorbers, enrichment and burnup increases.
- Syllabus of tutorials:
BISON and FAST codes will be introduced to students and they will perform basic validation calculations using both codes. Coupling of thermomechanical and thermohydraulic codes will be then presented with a focus on testing the safety and operational limits. Using these advanced tools, new fuel design will be also evaluated and discussed.
- Study Objective:
- Study materials:
K. Whittle: Nuclear Materials Science, Bristol, UK: IOP Publishing Ltd, 2016
NEA/OECD: Nuclear Fuel Safety Criteria Technical Review (Second Edition), OECD Publishing, 2012
Hales J. et al.: BISON Theory Manual The Equations behind Nuclear Fuel Analysis, Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2016
Was G.S.: Fundamentals of Radiation Materials Science, New York, NY: Springer New York, 2017
U.S. NRC: NRC: 10 CFR Appendix A to Part 50—General Design Criteria for Nuclear Power Plants, on-line: https://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-appa.html
NEA/OECD: State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels, vol. 2018
- Further information:
- No time-table has been prepared for this course
- The course is a part of the following study plans: