Detailed Evaluation of RCS Boundary Rupture during High-Pressure Severe Accident Sequences

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概要

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• A depressurization possibility of the reactor coolant system (RCS) before a reactor vessel rupture during a high-pressure severe accident sequence has been evaluated for the consideration of direct containment heating (DCH) and containment bypass. A total loss of feed water (TLOFW) and a station blackout (SBO) of the advanced power reactor 1400 (APR1400) has been evaluated from an initiating event to a creep rupture of the RCS boundary by using the SCDAP/RELAP5 computer code. In addition, intentional depressurization of the RCS using power-operated safety relief valves (POSRVs) has been evaluated. The SCDAPRELAP5 results have shown that the pressurizer surge line broke before the reactor vessel rupture failure, but a containment bypass did not occur because steam generator U tubes did not break. The intentional depressurization of the RCS using POSRV was effective for the DCH prevention at a reactor vessel rupture.

• 2011-11-01

著者

• HONG Seong-Wan

  Korea Atomic Energy Research Institute

• Hong Seong-wan

  Korea Advanced Institute Of Science And Technology

• Park Rae-joon

  Korea Atomic Energy Res. Inst.

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• Experimental Investigations on In-Vessel Corium Retention through Inherent Gap Cooling Mechanisms
• Detailed Evaluation of RCS Boundary Rupture during High-Pressure Severe Accident Sequences

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