Strategy Evaluation for Cavity Flooding during an ESBO Initiated Severe Accident

Abstract

Intentional depressurization and cavity flooding are two important measures in current severe accident management guidelines (SAMGs). An extreme scenario of an extended station blackout (ESBO), when electric power is unavailable for more than 24 hours, actually occurred in the Fukushima Daiichi accident and attracted lots of attention. In an ESBO, the containment spray cannot be activated for condensation, and, thus, cavity flooding will generate a large amount of steam, which, ironically, overpressurizes the containment to failure before the reactor vessel is melted through. Therefore, consideration of these conflicting issues and the ways in which plants operate is crucial for strengthening the strategies outlined in SAMGs. In this paper, the effects of intentional depressurization and cavity flooding in an ESBO for a representative 900 MW second-generation pressurized water reactor (PWR) are simulated with MAAP4 code. Diverse scenarios with different starting times of depressurization and water injection are also compared to summarize the positive and negative impacts for accident mitigation. The phenomena associated with creep ruptures, hydrogen combustion, corium stratification, and cavity boiling are also analyzed in detail to strengthen our understanding of severe accident mechanisms. The results point out the facility limitations of second-generation PWRs which can improve existing SAMGs.

A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident

“…If the other chemical reactions were considered all together, it may reach to 60,000 kg of the MCCI gas in Figure 18. Similar result could be found in MAAP4 calculation [27].…”

Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario

“…For large distributed reactors, scholars at home and abroad have conducted many studies on severe accidents caused by SBO. Common systematic analysis severe accident analysis codes MAAP and MELCOR have been used to calculate the accident sequence process of different large distributed nuclear power plants under severe accidents caused by SBO, and the mitigation capacity of related safety facilities has been calculated and evaluated [1][2][3][4]. In addition, the phenomena in the SBO transient process and safety system design are the hot research area.…”