Nuclear Reactor Theory

Course Description

Neutron transport equation. Multigroup diffusion theory. Calculation of fast spectrum and fast group constants. Calculation of thermal spectrum and thermal group constants. Unit cell calculation of heterogeneous reactor. Global calculations of reactor core. Analysis of nuclear fuel depletion. In-core fuel management methods. Modeling of control rods and burnable absorbers. Design of loading pattern for reload core. Nuclear reactor kinetics and reactor dynamics. Validation and verification of reactor modeling.

Study Programmes

Postgraduate doctoral study programme

Literature

James J. Duderstadt, Louis J. Hamilton (1976.), Nuclear Reactor Analysis, Wiley
Weston M. Stacey (2018.), Nuclear Reactor Physics, John Wiley & Sons
Yigal Ronen (Editor) (1986.), CRC Handbook of Nuclear Reactors Calculations, CRC Press, Boca Raton, FL
Alain Hébert (2009.), Applied Reactor Physics, Presses inter Polytechnique
Dan Gabriel Cacuci (Editor) (2010.), Handbook of Nuclear Engineering, Springer Science & Business Media

For students

General

ID 154740
  Summer semester
6 ECTS
L0 English Level