Nuclear Safety
Code 1097I
Credits 12
Learning outcomes
The objective of the course is to give to the students a sufficient knowledge in nuclear safety, with particular reference to the following items:
- the nuclear safety methodology and related procedure of licensing in USA (10 CFR Parts 50, 20 e 100; General Design Criteria and Regulatory Guides, safety goals)
- the objectives and the fundamental safety principles of IAEA (INSAG 3 and 12)
- the nuclear safety methodologies based on reliability: proposed by Farmer in UK and in Italy by Galvagni, the Canadian safety methodology
- the main aspects of Italian legislation on nuclear safety: the licensing iter for the construction and operation of nuclear power plants; the nuclear emergency planning.
- the siting of NPP
- the Rasmussen report (WASH 1400)
- the accidents in LWR and design principles of the main safety and protection systems; in depth treatment of LOCA and RIA;
- the severe accidents: phenomenology and methods of analysis
- the containment systems of Nuclear Power Plants (NPP) and related operation principles; the main engineering safeguard systems associated to the containment (spray, filters, H2 treatment)
- the source term for accidents in LWR
- PSA of NPP
- peculiar aspects of accidents in CANDU NPP
- peculiar aspects of accidents in Liquid Metal FBR
- the criticality accidents
- the INES scale of IAEA for nuclear accidents classification
- the safety culture
- the costs-risks-benefits analysis and the environmental impact of the various energy cycles.
For the practical activities, in addition to simple exercises on the various items abovementioned, the preliminary safety reports of current NPPs as described in relevant documents and examples will be discussed, in such a way to apply and verify the knowledge acquired in the lessons. Some informatics instruments will be used for NPP accidents analysis (IAEA NPP Simulator, GOTHIC and FUMO for containment analysis, MELCOR for severe accident analysis),. The aim is to develop in the students the capability for a correct and knowledge based use of these instruments for study the physical and chemical phenomena which characterize the main nuclear accidents and for solving nuclear safety problems.
Finally the TMI2, Chernobyl and Fukushima accidents and related lessons will be discussed.
- the nuclear safety methodology and related procedure of licensing in USA (10 CFR Parts 50, 20 e 100; General Design Criteria and Regulatory Guides, safety goals)
- the objectives and the fundamental safety principles of IAEA (INSAG 3 and 12)
- the nuclear safety methodologies based on reliability: proposed by Farmer in UK and in Italy by Galvagni, the Canadian safety methodology
- the main aspects of Italian legislation on nuclear safety: the licensing iter for the construction and operation of nuclear power plants; the nuclear emergency planning.
- the siting of NPP
- the Rasmussen report (WASH 1400)
- the accidents in LWR and design principles of the main safety and protection systems; in depth treatment of LOCA and RIA;
- the severe accidents: phenomenology and methods of analysis
- the containment systems of Nuclear Power Plants (NPP) and related operation principles; the main engineering safeguard systems associated to the containment (spray, filters, H2 treatment)
- the source term for accidents in LWR
- PSA of NPP
- peculiar aspects of accidents in CANDU NPP
- peculiar aspects of accidents in Liquid Metal FBR
- the criticality accidents
- the INES scale of IAEA for nuclear accidents classification
- the safety culture
- the costs-risks-benefits analysis and the environmental impact of the various energy cycles.
For the practical activities, in addition to simple exercises on the various items abovementioned, the preliminary safety reports of current NPPs as described in relevant documents and examples will be discussed, in such a way to apply and verify the knowledge acquired in the lessons. Some informatics instruments will be used for NPP accidents analysis (IAEA NPP Simulator, GOTHIC and FUMO for containment analysis, MELCOR for severe accident analysis),. The aim is to develop in the students the capability for a correct and knowledge based use of these instruments for study the physical and chemical phenomena which characterize the main nuclear accidents and for solving nuclear safety problems.
Finally the TMI2, Chernobyl and Fukushima accidents and related lessons will be discussed.