(in Polish) Fizyka reaktorów jądrowych 1100-4FRJ
Lecture plan:
1. Basic properties of neutrons
2. Nuclear cross-section and reactions
3. Neutron balance and criticality
4. Delayed neutrons and reactor dynamics
5. Neutron flux and current
6. One-dimensional neutron diffusion theory
7. Problems with external neutron source
8. Problems with fissionable material
9. Neutron reflector
10. Homogenization
11. Numerical methods
12. Multigroup diffusion theory
13. Neutron transport theory
Main fields of studies for MISMaP
physics
Mode
Prerequisites (description)
Learning outcomes
Student understands basics of nuclear reactor operations, approximations and methods of solving of presented problems. Knows how to solve basic problems if kinetic and dynamics of reactor.
Assessment criteria
During the lecture a number of problems to solve will be given to students. A final grade or a oral exam will be proposed based on results.
Bibliography
* DOE Fundamentals Handbook, "Nuclear Physics and Reactor Theory", Volume 1 and 2, U.S. Department of Energy, 1993
* Weston M. Stacey, Nuclear Reactor Physics 2nd edition, Wiley-VCH, 2007
* Raymond L. Murray, Keith E. Holbert, "Nuclear Energy", 7th Edition, Elsevier 2015
Additional information
Additional information (registration calendar, class conductors, localization and schedules of classes), might be available in the USOSweb system: