Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor

Table 2

Key events of accident sequence.

KEY EVENT	TIME (s)
LOCA	0
Reactor emergency shutdown (SCRAM) initiating (evaluating system delay)	0.2
Turbine trip initiating	0.2
Trip of recirculation pumps initiating	0.3
Core Uncovers/ First heat up of the core	32
Core fully uncovered	50
Oxidation onset	292
= 1473 K (1200°C)	421
Start of core relocation to lower head	847
Dry out of the lower head	3000