Nuclear Safety

Course Description

Safety requirements during design, construction and operation of nuclear power plant. Defense in depth safety concept. National and international safety regulations. Safety analysis and environmental report of the plant. Safety analysis methods. Deterministic analyses. Component and system models in thermalhydraulics system codes. Thermalhydraulics calculation. Thermal and mechanical calculation of the fuel rod. Probabilistic risk analiyses, fault tree and event tree methods. Design bases accidents. Severe reactor accidents. Fire hazard and external initiating events. Radioactive effluent release and consequence analysis. Safety assessment of radioactive waste storage facilities. Risk analysis.

General Competencies

Understanding of basic safety principles applied in NPP design and operation. Knowledge of regulatory and licensing requirements. Preparation of the safety assessments, conducting of safety reviews for nuclear ficilities.

Learning Outcomes

  1. describe main safety problems as apply to nuclear power plants
  2. explain defense-in-depth concept
  3. apply standard computer codes for safety analyses
  4. prepare input data for simple thermal-hydraulic accident calculations
  5. classify different types of nuclear accidents
  6. analyze results of system codes safety calculations
  7. estimate nuclear power plant radiological influence
  8. analyze importane of probabilistic safety analyses

Forms of Teaching


Teaching the course is organized in two teaching cycles. The first cycle contains seven weeks, mid-term exam, and the second cycle contains six weeks of classes and a final exam. Classes are conducted through a total of 15 weeks with weekly load of 2 hours. Each lecture includes wrriten material and slides.


Solved examples to support lectures and prepare students for exams. 1 hour per week. Solved examples on slides and discussion of possible variations in problem statement with examples on bord.


Application of computer code for calculation of transients in primary system, nuclear fuel and containment. Release of effluents in the environment.

Grading Method

Continuous Assessment Exam
Type Threshold Percent of Grade Threshold Percent of Grade
Homeworks 0 % 15 % 50 % 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. Intoduction, risk and NPPs, histiry and regulatory requirements
  2. Safety philosophy, design priciples
  3. Design bases accidents, design margins, safety functions
  4. Safety systems (PWR)
  5. Deterministic safety analyses, mathematical models
  6. Licensing, safety analysis report, siting of NPPs
  7. Accidents related to change in reactor coolant inventory
  8. Exams
  9. Exams
  10. Accidents related to reactivity changes, ATWS and loss of primary circulation
  11. Accidents related to change in secondary heat transfer rate
  12. Containment response during DBAs
  13. Severe reactor accidents
  14. Probabilistic safety analyses (ET, FT, CDF, cut set)
  15. Radioactive effluents dispersion, consequences of radioactivity release, emergency planning

Study Programmes

University graduate
Electrical Power Engineering (profile)
Specialization Course (2. semester)


Gianni Petrangeli (2006.), Nuclear Safey, Butterworth-Heinemann
E.E. Lewis (1978.), Nuclear Power Reactor Safety, John Wiley
B. Pershagen (1989.), Light Water Reactor Safety, Pergamon Press
N.E. Todreas, M.S. Kazimi (1989.), Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Hemisphere Publishing Corporation


For students


ID 86485
  Summer semester
L1 English Level
L1 e-Learning
30 Lectures
15 Exercises
0 Laboratory exercises
0 Project laboratory

Grading System

90 Excellent
75 Very Good
60 Good
50 Acceptable