Nuclear Safety

Data is displayed for academic year: 2023./2024.

Lecturers

Prof.
Davor Grgić
Assoc. Prof.
Siniša Šadek

Course Description

Safety principles in the design and operation of a nuclear power plant. International and national regulations. Power plant safety report and environmental impact report. Systematization and classification of faults/accidents. Methods for safety analyses. Deterministic safety analyzes. Modeling of nuclear power plant components and systems. Thermohydraulic system and core calculations. Thermal and mechanical calculation of fuel. Analysis of design basis accidents. Severe reactor accidents. Fire and external fault initiators (seismic). Analysis of the discharge of radioactive material from a nuclear power plant (leakage of containment, dispersion into the environment, radiological consequences). Safety assessment of radioactive waste storage.

Study Programmes

University graduate
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Specialization Course (1. semester) (3. semester)

Learning Outcomes

  1. Describe the basic safety concerns of nuclear power plants
  2. Explain the defence-in-depth strategy
  3. Apply existing safety analysis programs
  4. Prepare input data for simple safety calculations
  5. Classify different nuclear accidents
  6. Analyze calculation results with system codes
  7. Assess the radiological impact of the plant operation on the environment
  8. Analyze the importance of probabilistic safety analyzes

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. Defence in depth concept, active and passive safety, Redundancy, diversity, physical separation, single failure criteria
  2. Environmental and equipment qualification, Control systems, process and nuclear instrumentation
  3. Reactor protections systems, set-points, margins, Engineering safety features, critical safety functions
  4. Thermal and mechanical model of fuel rod (fuel and cladding temparatues, cladding integrity), Two phase fluid flow and heat transfer, critical heat flow, critical mass velocity
  5. Condensation, noncondesables, aerosol behavior, H2 burn, Control volume concept and 6-equations 1D two phase flow models
  6. Nodal neutron diffuison codes and coupling
  7. Containment models and severe accident integrated codes
  8. Midterm exam
  9. In-vessel phase, Core degradation and melt, Fuel cladding oxidation; Hydrogen release
  10. Ex-vessel phase; Containment behaviour, Reactor pressure vessel and containment integrity, NPP severe accidents (TMI, Chernobyl, Fukushima)
  11. Geology, liquefaction, and seismic requirements, Hydrology, floods, weather conditions, Population density, transpot and industrial objects
  12. Primary and secondary source term, release categories for gas and liquid effluents
  13. Atmospheric dispersion, migration of radioactive material in soil, Protective action guidelines for sheltering, evacuation, relocation
  14. Bilogical effects of radioactive materials, health risk
  15. Final exam

Literature

(.), E.E. Lewis (1978.), Nuclear Power Reactor Safety, John Wiley,
(.), Gianni Petrangeli (2006.), Nuclear Safey, Butterworth-Heinemann,
(.), B. Pershagen (1989.), Light Water Reactor Safety, Pergamon Press,

For students

General

ID 222516
  Winter semester
5 ECTS
L1 English Level
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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