Nuclear Engineering

Data is displayed for the academic year: 2025./2026.

Course Description

Description of the fission reaction. Neutron moderation and diffusion. Critical dimensions of the reactor. Reflector. Reactivity control devices. Kinetic equations. Reactivity feedbacks. Neutronic and thermal steady state reactor calculations. Reactor types. Operational characteristics. Nuclear power plant technological, auxiliary and safety systems. Reactor regulation and protection system. Principles of nuclear power plant design. Class 1E electrical equipment. Advanced nuclear reactors.

Study Programmes

University graduate
[FER3-EN] Control Systems and Robotics - profile
Elective courses (2. semester)
[FER3-EN] Electrical Power Engineering - profile
Elective courses (2. semester)

Learning Outcomes

  1. Describe the basic reactions with neutrons
  2. Apply the mass defect principle to the calculation of the energy yield of nuclear reactions
  3. Explain conditions for reactor criticality
  4. Identify the reasons for the reactivity change during the NPP operation
  5. Explain the role of basic components in the light-water reactors
  6. Analyze the behavior of the nuclear reactor during operation
  7. Analyze power and temperature distribution in the reactor core
  8. Analyze operating conditions of electrical equipment in the nuclear power plant

Forms of Teaching

Lectures

Lectures will provide a theoretical background to the students.

Exercises

These will be used to solve numerical examples to the students.

Laboratory

Solving practical examples using computer simulation.

Grading Method

Continuous Assessment Exam
Type Threshold Percent of Grade Threshold Percent of Grade
Homeworks 0 % 15 % 0 % 15 %
Mid Term Exam: Written 0 % 30 % 0 %
Final Exam: Written 0 % 45 %
Final Exam: Oral 10 %
Exam: Written 0 % 75 %
Exam: Oral 10 %

Week by Week Schedule

  1. Binding energy and mass defect, Fission reaction, energy distribution and decay heat
  2. Fusion reaction, conditions to get sustainable reaction
  3. Microscopic and macroscopic cross section concept, energy spectra
  4. Eleastic and inelastic scattering, neutron slowing down with and without absorption
  5. One and multi group neutron diffusion equation
  6. Solution of reactor diffusion equation
  7. Reflected reactor, Control absorbers
  8. Midterm exam
  9. Reactor kinetics (one and 6 groups)
  10. Temperature effects on reactivity
  11. Reactor poisoning and fuel depletion
  12. Analytical solution of reactor diffusion equation
  13. Numerical solution in 1D, 2D and 3D, peaking factors
  14. Single phase fluid flow and heat transfer in reactor channel, DNBR, fuel rod thermal model
  15. Final exam

Literature

(.), D. Feretić (2010.), Uvod u nuklearnu energetiku, Školska knjiga,
(.), D. Feretić, N. Čavlina, N. Debrecin (1995.), Nuklearne elektrane, Školska knjiga,
(.), John R. Lamarsh and Anthony J. Baratta (2001.), Introduction to Nuclear Engineering, Prentice Hall,

General

ID 222988
  Summer semester
5 ECTS
L1 e-Learning
30 Lectures
0 Seminar
15 Exercises
8 Laboratory exercises
0 Project laboratory
0 Physical education excercises

Grading System

90 Excellent
75 Very Good
60 Good
50 Sufficient

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