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. The strategy denoted as “in-vessel retention (IVR)” is widely usedin severe accident (SA) management by most advanced nuclear powerplants. The essence of IVR mitigation is to provide long-termexternal water cooling in maintaining the reactor pressure vessel(RPV) integrity. Actually, the traditional IVR concept assumed thatRPV was fully submerged into the water flooding, and the meltingpool was depressurized during the SA. The above assumptions weren'tseriously challenged until the occurrence of Fukushima accident on2011, suggesting the structural behavior had not been appropriatelyassessed. Therefore, the paper tries to address thestructure-related issue on determining whether RPV safety can bemaintained or not with the effect of various water levels andinternal pressures created from core meltdown accident. In achievingit, the RPV structural behaviors are numerically investigated interms of several field parameters, such as temperature, deformation,stress, plastic strain, creep strain, and total damage. Due to thepresence of high temperature melt on the inside and water cooling onthe outside, the RPV failure is governed by the failure mechanismsof creep, thermal-plasticity and plasticity. The creep and plasticdamages are interacted with each other, which further accelerate thefailure process. Through detailed investigation, it is found thatthe internal pressure as well as water levels plays an importantrole in determining the RPV failure time, mode and site.

Structural integrity investigation for RPV with various cooling water levels under pressurized melting pool