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- Corium (Nuclear Reactor) - an overview | ScienceDirect Topics
The so-called ‘corium’ or fuel-containing material, a mixture of fuel, debris and molten metal, can fall onto a ‘core catcher’ and be thus spread out efficiently and cooled so that its progression is stopped and the containment remains tight, thus maintaining its DID design requirement to prevent the uncontrolled release of radioactive
- Numerical simulation on thermal-hydraulic-mechanical coupling of core . . .
The majority of corium migrates close to the wall of the RPV lower head, causing the temperature at the edges of the lower support plate to exceed that at the center, leading to creep failure under thermal stress As the corium continues to migrate, the cumulative mass of molten material and the convective heat transfer coefficient increase
- Thermophysical properties of liquid UO2, ZrO2 and corium by molecular . . .
In predicting thermophysical properties of liquid state of corium, it is important to design the initial configuration of liquid state (position of every ion and its interactions) In this work, the UO 2 and ZrO 2 systems are fluorite crystals and are first melted at very high temperatures (around 5000 K) under the NPT ensemble for 20 ps with
- Experimental contribution to the corium thermodynamic modelling – The U . . .
Many phenomena take place during Molten Corium Concrete Interaction MCCI (Journeau and Piluso, 2012): high temperature concrete decomposition, heat transfer due to gas bubbles agitation, formation of several phases, oxidation of metals, etc Several studies on the interaction between corium and concrete were published starting from the 1980s
- Products of molten corium-metal interaction in chernobyl accident . . .
In experiments on the interaction of molten corium pool with steel, stratification of layers covering the full range between initial steel and solidified corium is observed (Beshta et al , 2001, 2006) This is an expected situation due to mere geometry of the experiment: macroscopic amounts of molten corium in a steel crucible will stratify
- An investigation of corium in Fukushima Daiichi Unit-1 accident
Corium is a radioactive mixture of nuclear fuel, cladding, control rods, fission products, and structural materials The main materials involved are uranium dioxide (UO 2 ) for the fuel; zirconium as cladding and the fuel channel; and boron carbide (B 4 C) for the control rods and different varieties of steel for control rod cladding and
- Thermodynamic analysis for molten corium stratification with U-Zr-O-Fe . . .
Jiang et al [14] successfully predicted the molten corium stratification under all experimental conditions in the STFM-Fe tests of the MASCA project by establishing the self-consistent U-Zr-O-Fe database using the associate model for the liquid phase, but the effects of B and C on the molten corium stratification were not considered
- Study on corium-concrete interaction, heat transfer, and concrete . . .
The concrete ablation modeling is a complex process as it depends on various parameters including (a) decay heat, (b) mass flux from molten corium, (c) different reactions during corium and concrete interaction, (d) heat transfer and slag movement into the molten corium, and (f) transfer of heat to the surroundings
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