Masters Course in Nuclear Engineering

Lecture 1
Historical overview of accidents in nuclear installations

Lecture 2
Core heat-up, cladding rupture and oxidation; essentially intact core reflooding

Lecture 3
Early phase core degradation and degraded core reflooding

Lecture 4
Core melting, relocation and late phase interactions in reactor vessel; vessel failure and corium ejection

Lecture 5
In- and ex-vessel molten fuel coolant interaction

Lecture 6
Spent fuel pool accidents, H2 generation, FP release

Lecture 7
Molten corium and concrete interaction and gas and aerosol release

Lecture 8
Containment thermal-hydraulics and H2 distribution; risk of deflagration/detonation, mitigation systems

Lecture 9
Fission product release from fuel, aerosol formation, transport in reactor coolant system

Lecture 10
Fission product behaviour in containment; aerosol transport/deposition, iodine chemistry

Lecture 11
In- and ex-vessel corium retention

Lecture 12
Severe Accident Management and Mitigation on current NPPs

Lecture 13
Fukushima

Lecture 14
Consequences of severe accidents; health and land contamination, public opinion, nuclear programmes

Lecture 15
Analytical Techniques for Simulation of Beyond Design Basis Accidents