Evaluation of safety and risk in medical physics

Regular enrolement

Fundamentals of radiation and nuclear safety
Identification and quantification of the risks
Methods of analysis of the potential hazards in radiation and nuclear activities
Human factor
Mathematical fundamentals and analytical tools
Probabilistic safety analysis
Damage decision tree
Events decision tree
Deterministic safety analysis
Risk assessment
Sources of uncertainty and evaluation of computer based predictions
Quality assurance and control.

• A.Kuhlman, Introduction to Safety Science, Springer Verlag, 1985.
• A.Kletz, HAZOP & HAZAN, Notes on the Identification and Assessment of Hazards (2nd ed.). Loss Prevention (The Institution of Chemical Engineers), Warwickshire, 1986.
• Ian S.Sutton, Process Reliability Risk Management, Van Nostrand Reinhold, 1991.
• J.S.Arendt, D.K.Lorenzo, A.F.Lusby, Evaluating Process Safety in the Chemical Industry (A Manager's Guide to Quantitative Risk Assessment), JBF Associates, Inc. New York, 1989.
• N. P.Cheremisinnoff: Practical Guide to Industrial Safety, Marcel Dekker, Inc. NY 2001

Students learn about deterministic and probabilistic methods for evaluation of reliability and safety in activities involving radiation, as well as for exposure optimization and minimization of risk.

Knowledge and understanding:
Understanding of deterministic and probabilistic methods and tools for risk and safety assessment.
Application:
Ability to analyze the safety and reliability application of radiation facilities.
Reflection:
A critical assessment of theoretical predictions with results of measurements.
Transferable skills:
Ability to collect data, interpretation and evaluation of the results of measurements.

Lectures, seminar, practical excercises at the TRIGA reactor.

2 tests with problem solving, written exam (problem solving)
Oral exam (questions from lectures)
grading: 5 (fail), 6-10 (pass) (according to the Statute of UL)

1. BERAR, Ovidiu-Adrian, PROŠEK, Andrej, MAVKO, Borut. RELAP5 and TRACE assessment of the Achilles natural reflood experiment. Nuclear Engineering and Design, ISSN 0029-5493. [Print ed.], avg. 2013, vol. 261, str. 306-316
2. URŠIČ, Mitja, LESKOVAR, Matjaž, MAVKO, Borut. Material properties' influence in fuel-coolant interaction codes. Journal of engineering for gas turbines and power, ISSN 0742-4795, 2010, vol. 132, no. 7, str. 072901-1-072901-7.
3. KONČAR, Boštjan, MAVKO, Borut. Wall function approach for boiling two-phase flows. Nuclear Engineering and Design, ISSN 0029-5493. [Print ed.], 2010, vol. 240, no. 11, str. 3910-3918