Abstract
Core damage and melt progression behavior due to loss of core cooling function is one of the important factors in the severe accident. After TMI-2 accident, some integral severe accident analysis codes have been developed; however, the core damage behaviors, the relocation behavior of molten core debris and failure modes of reactor pressure vessel have still large uncertainty. The Atomic Energy Society of Japan (AESJ) developed a new thermal-hydraulics safety evaluation fundamental technology enhancement strategy roadmap (TH-RM) for LWR safety improvement and development after Fukushima Daiichi NPP accident. This paper describes the major technical issues and activities to secure the integrity of reactor pressure vessel which are discussed in the TH-RM developing process.
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