Strategy Evaluation for Cavity Flooding during an ESBO Initiated Severe Accident
Creators
- 1. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China
- 2. China Nuclear Power Operation Technology Corporation LTD, Wuhan 430000, China
Description
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.
Files
10.1155_2018_8680406.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2018/8680406;
- Crossref Funder ID
- 10.13039/501100001809;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2018
- Journal Page Range
- 1-15
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENT MANAGEMENT; CONTAINMENT; CORIUM; CREEP; DEPRESSURIZATION; ELECTRIC POWER; FUKUSHIMA ACCIDENT DATA; MELTDOWN; MITIGATION; PWR TYPE REACTORS; RCIC SYSTEMS; REACTOR VESSELS; RUPTURES; SEVERE ACCIDENTS; STATION BLACKOUT; STRATIFICATION
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINERS; COOLING SYSTEMS; DATASETS; DOCUMENT TYPES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; FUKUSHIMA ACCIDENT ARCHIVE; MANAGEMENT; MECHANICAL PROPERTIES; POWER; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SEVERE ACCIDENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- © Author(s)
- Contract/Grant/Project number
- 11705035, HEUCFJ171501
- Notes
- Record automatically processed
- Funding organization
- National Natural Science Foundation of China, Harbin Engineering University