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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
- 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
- Natural convection heat transfer in corium pools: A review work of . . .
In-vessel corium is a mixture made up from molten core materials, which are composed of (U, Zr)O 2 + Zr + Fe + B 4 C + fission products The corium is characterized by the degree of oxidization of zirconium and U Zr ratio and has a solidus-liquidus temperature of 1500–2850 °C (Sehgal, 2012) So far, due to technological limitations, only a
- An investigation of corium in Fukushima Daiichi Unit-1 accident
We can notice from the tables that, the total corium activity10 years post –accident was 6 046E+17Bq and the specific activity was about 4 3E+12Bq kg, assuming homogeneous mixture and 50% of the volatile radio-nuclides Also, the total corium activity 50 years post-accident was 1 89 E+17Bq and the specific activity was about1 35E+12Bq kg
- Viscosity models for corium melts - ScienceDirect
We calculated the viscosity of basalts and basalt with 18%wt of UO 2, and then, pending direct measurements of liquid corium viscosity, we tried to determine the range of applicability of this method to corium-concrete mixtures In the second part, we looked for an apparent viscosity model which takes account of the increase of solid volume
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