The goal of the course is to train the students for the field of nuclear energy using fission reactors. The students acquire comprehensive knowledge on the physics of nuclear fission reactors: neutron flux, cross sections, fission, breeding processes, chain reaction, critical size of a nuclear system, moderation, reactor dynamics, transport- and diffusion-equation for the neutron flux distribution, power density distributions in reactor, one-group, two-group and multi-group theories for the neutron spectrum. Students are able to analyze and understand the obtained results. Based on the reactor physics knowledge, the students are able to understand, compare and evaluate the capabilities of different types of reactors - LWR, heavy water reactors, nuclear power systems of generation IV – as well as their fundamental nuclear safety concepts. The students are qualified for further training in nuclear energy and safety field and for (also research-related) professional activity in the nuclear industry.

• nuclear fission & fusion,
• radioactive decay, neutron excess, fission, fast and
  thermal neutrons, fissile and fertile nuclei,
• neutron flux, cross section, reaction rate, mean free path,
  chain reaction, critical size, moderation,
• reactor dynamics,
• transport- and diffusion-equation for the neutron flux distribution,
  power distributions in reactor,
• one-group and two-group theories,
• light-water reactors,
• reactor safety,
• design of nuclear reactors,
• breeding processes,
• nuclear power systems of generation IV

Dieter Schmidt, Reaktortechnik, Band 1: Grundlagen, ISBN 3 7650 2003 6

Dieter Schmidt, Reaktortechnik, Band 2: Anwendungen, ISBN 3 7650 2004 4

Di  (30.07.2024), 09:00 bis 17:00
Do (01.08.2024), 09:00 bis 17:00
Fr  (02.08.2024), 09:00 bis 17:00