Nuclear Fuel Cycle
- Department of Nuclear Reactors
The course deal with introduction to the nuclear fuel cycle of nuclear power plants, particularly PWR which are in operation in the Czech Republic or are under consideration for operation in future in the Czech Republic. The first part of the course is focused on front-end of the nuclear fuel cycle, the second part is focused on fuel utilisation in the reactor core and the third part of the course is focused on back-end of the nuclear fuel cycle.
- Syllabus of lectures:
1.Introduction, uranium supply, uranium mining (1 lecture): definition and description of the fuel cycle, different types of fuel cycles, uranium reserves in the World, uranium mining and milling, uranium mining in the Czech Republic
2.Ore processing, yellow cake and conversion to UF6 (1 lecture): mechanical processing of ore, leaching process and methods of separation of uranium, production of yellow cake, definition of nuclear purity, production of UF6
3.Uranium enrichment (1 lecture): definition of terms, history, theory, description of enrichment methods: thermal diffusion, chemical separation, electromagnetic sep., aerodynamic sep., diffusion gas, centrifugation, AVLIS
4.Fuel fabrication (1 lecture): conversion of UF6 to UO2, production of pelets, fabrication of fuel rods and assemblies
5.Nuclear fuel in nuclear power plant (1 lecture): PWR fuel design and fuel technology with focus on VVER fuel, fresh and spent fuel storing and handling at the nuclear power plant
6.Uranium fuel in reactor core (1 lecture): uranium fuel in PWR core, changes in the fuel during burn-up, absorbers, fission products, influence of xenon and samarium to a reactor operation
7.Thorium and MOX fuel, new reactor generations’ fuels (1 lecture): specific features of use of thorium and MOX fuel in a reactor core, BWR, graphite and FBR fuels, new reactor generations’ fuels
8.Used and spent nuclear fuel (1 lecture): actually burning, spent and used nuclear fuel, inventory of the used and spent nuclear fuel, software for used and spent nuclear fuel inventory calculation.
9.Used nuclear fuel storing (2 lectures): technical and legislation requirements for used nuclear fuel dry and wet storage, physical, technical, and legal requirements for containers, transport and storage containers. CASTOR container.
10.Spent nuclear fuel reposition (1 lecture): basic technical and legal requirements for spent nuclear fuel reposition, permanent repositories, situation in the Czech Republic.
11.Used nuclear fuel reprocessing (1 lecture): state of the art of reprocessing, perspectives of used nuclear fuel reprocessing in the world, MOX fuel, La Hague reprocessing plant in France.
- Syllabus of tutorials:
- Study Objective:
- Study materials:
Lamarsh J.R, Baratta A.J.: Introduction to Nuclear Engineering. London: Pearson, 2017. ISBN 978-0134570051
IAEA: Status and Trends in Spent Fuel and Radioactive Waste Management, Nuclear Energy Series No. NW-T-1.14, Vienna, 2018
Crossland, I.: Nuclear fuel cycle science and engineering. 1st ed. Cambridge, UK: Woodhead Pub., 2012, ISBN: 9780857090737
Cochran R.G., Tsoulfanidis N.: Nuclear Fuel Cycle: Analysis and Management, American Nuclear Society, 1999, ISBN: 9780894484513
- Further information:
- No time-table has been prepared for this course
- The course is a part of the following study plans: