Probabilistic Risk Assessment for Nuclear Facilities 1100-PRA

The course covers the following modules:
1. Introduction to nuclear risk and PRA
2. Probability and reliability fundamentals
3. Event tree and fault tree analysis
4. Reliability data and component modeling
5. Human reliability analysis
6. Common-cause failure analysis
7. Lifetime simulation of system performance
8. Uncertainty and sensitivity studies
9. Level 1 PRA: Core damage frequency
10. Level 2 PRA: Containment performance
11. Level 3 PRA: Offsite consequences
12. Emerging applications of PRA

Kierunek podstawowy MISMaP

fizyka

Koordynatorzy przedmiotu

Agnieszka Korgul

Rodzaj przedmiotu

uzupełniające
nieobowiązkowe

Tryb prowadzenia

w sali

Założenia (opisowo)

Specialist (Lectures + computer laboratories) This course introduces the principles, methods, and applications of Probabilistic Risk Assessment (PRA) for nuclear facilities. The course will be delivered by external lecturers from the National Centre for Nuclear Research (NCBJ), bringing practical experience from research and safety assessment activities in the nuclear sector. The lectures will be conducted by Dr. Hab. Eng. Karol Kowal, while the exercise sessions will be led by Dr. Eng. Aleksej Kaszko. Their expertise will provide students with both a solid theoretical foundation and practical insights into the application of PRA methods in nuclear safety analysis.

Efekty kształcenia

Upon successful completion of the course, students will be able to:
1. Explain the role of PRA in nuclear safety and regulation.
2. Apply probability and reliability concepts to nuclear systems.
3. Construct and analyse fault trees and event trees.
4. Quantify core damage frequency and other risk metrics.
5. Evaluate human and common-causes contributions to risk.
6. Perform lifetime simulations of system performance.
7. Perform basic uncertainty and sensitivity analyses.
8. Interpret Level 1, Level 2, and Level 3 PRA results.
9. Critically assess PRA studies and risk-informed decisions.
10. Apply PRA concepts to modern nuclear technologies.

Kryteria oceniania

1. PRA model developed for selected system using software (50%).
2. Written exam – test with possible open-ended questions (50%).

Literatura

1. John C. Lee, Norman J. McCormick, Risk and Safety Analysis of Nuclear Systems, John Wiley & Sons, 2011.
2. Ralph R. Fullwood, Probabilistic Safety Assessment in the Chemical and Nuclear Industries, Butterworth-Heinemann, 2011.
3. Romney B. Duffey, John Walton Saull, Managing Risk: The Human Element, Wiley & Sons, 2008.
4. Nozer D. Singpurwalla, Reliability and Risk: A Bayesian Perspective, Wiley & Sons, 2006.
5. The IAEA reports and guidelines on the leading topics of the course.