Sandia National Laboratory instructors present a five-day training course on the different methodologies for addressing accident consequence (Level-3) analysis accepted by regulatory bodies and available in the nuclear power plant industry, complemented with hands-on exercises in the quantification techniques for Level-3 using WinMACCS. The training specifically covers the following topics:
- Discussions of the international PRA practices relevant to external releases
- Presentation of the characteristics of consequence analysis
- Discussions of the relationship between consequence and risk
- Development of the interface between Level II and Level III analysis
- Discussions of the modeling of atmospheric transport and dispersion
- Introduction to dosimetry and health effects modeling
- Modeling of emergency response
- Modeling of economic consequences
- Discussions of uncertainties in probabilistic risk assessment and consequence analysis
- Discussions of NUREG-1150 and the State-Of-the-Art Reactor Consequence Analysis (SOARCA),
- Interpretation of the results and applicability to the regulatory framework
- Discussions of some applications of consequence modeling