ScholarWorks@중앙대학교

초록

Following the Fukushima accident, controlling of hydrogen corresponding to a 100% metal-water reaction (MWR) has become a critical regulatory requirement. This study presents a systematic comparative analysis of containment pressure response for three PWR designs: Framatome, OPR1000, and APR1400 under a Station Blackout (SBO) scenario using the MELCOR code. The simulation results indicate that reactor design characteristics, specifically concrete composition and containment volume, significantly influence accident consequences. Unlike the OPR1000, which employs basaltic concrete, the Framatome and APR1400 designs employ limestone concrete, generating substantial carbon monoxide (CO) during the Molten Core-Concrete Interaction (MCCI) phase. Consequently, the Framatome design exhibited the highest peak pressure of 11.60 bar, driven by the highest volumetric energy density (3.93 MJ/m³), primarily due to its small containment free volume. Conversely, the APR1400, despite releasing the largest total combustion energy, showed a mitigated pressure rise (8.82 bar) due to its large free volume. A linear proportional trend between volumetric energy density and pressure rise was identified across the designs, demonstrating that containment capacity is a dominant factor in mitigating pressure loads from combustible gas generation.

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