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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
- 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
- Microstructure and mechanical properties of the LWR solidified melt . . .
X-ray structural studies of corium were carried out on the EMPYREAN diffractometer with the Rentgen-Master computer control system X-ray diffraction patterns were obtained using the monochromatic CuK α-radiation (λ Kα1 = 0 154056 nm) at an accelerating voltage of 30 kV and an anodic current of 40 mA with a scanning interval along the 2θ
- 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
- 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
- Numerical simulation on in-vessel molten corium behavior with external . . .
Because molten corium is a mixture, there is a mushy zone, which is a section where the physical properties change continuously with solidus temperature and liquidus temperature as the boundary when the phase changes In this study, the phase change is implemented by changing the physical properties
- A viscoplastic approach to corium spreading during a severe nuclear . . .
Lava and corium flows have been compared and arguments for the modeling of the latter as a non-isothermal free-surface viscoplastic flow have been presented Results on the spreading of corium using the model developed by Bernabeu et al (2016) have been compared to the VEU7 experiment (Journeau et al , 2006)
- 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
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