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Safety of Fusion Reactors  Chapter | 14    427


             APPENDIX A.14.2 REFERENCE EVENTS CONSIDERED
             IN THE ITER SAFETY ANALYSIS

             Note: (i) incident; (a) accident.
             Plasma events
                Loss of plasma control/off-design plasma behaviour (i, a)

             Loss of electric power supply
                Loss of electric power supply for up to 1 h (i)
                Loss of electric power supply for up to 32 h (a)
                Complete loss of on-site and off-site electrical power for up to 1 h (a)

             In-vessel cooling system events
                In-vessel FW cooling pipe or coolant channel leak (i)
                Multiple first-wall cooling pipes or coolant channels damage (a)
                Loss of vacuum through a vacuum vessel penetration line (a)
             Ex-vessel events in in-vessel heat-transfer system (HTS)
                Loss of heat sink in divertor HTS (i)
                Pump trip/loss of flow in divertor HTS (i)
                Pump seizure in divertor HTS (a)
                Rupture of vacuum pump cooling system (a)
                Large ex-vessel divertor HTS break (a)
                Heat exchanger leakage (i)
                Heat exchanger tube crack (a)
             Maintenance events
                Transport cask accidents (a)
                Vacuum vessel maintenance accidents (a)
             Tritium plant and vacuum system events
                Tritium delivery line leakage (i)
                Mishandling of the tritium-containing substrate transport (a)
                Isotope separation system failure (a)
                Fuelling line with impaired confinement (a)
             Magnet events
                Toroidal field coil short circuit (a)
                Poloidal field coil arc (a)
             Cryostat events
                Air ingress (a)
                Water/air/helium ingress (a)
             Hot cell events
                Failure of RSs confinement (a)
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