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- Corium (Nuclear Reactor) - an overview | ScienceDirect Topics
• corium: molten materials that are formed during the core melting accident in a nuclear reactor core, as well as their solidified products; corium usually contains fuel elements i e U, some fission products, and structural materials (Zr, Fe, Ni, Cr), •
- Development of ex-vessel corium coolability analysis program(COCCA . . .
KAERI developed a module named Code of Ex-vessel Corium Coolability Analysis (COCCA) to perform meaningful risk analyses and make decisions in the field of accident management, mitigation measures and emergency procedures through the ex-vessel corium coolability analysis COCCA code is a stand-alone, 1-D, and a fast running code to analyze the phenomena and sequences in the reactor cavity
- An investigation of corium in Fukushima Daiichi Unit-1 accident
The core melt composition resulting from the Fukushima Daiichi Unit1 Nuclear Power Plant (FD-U1) accident is essential for the corium characterization…
- Products of molten corium-metal interaction in chernobyl accident . . .
Pieces of molten corium – steel interaction products were also entrapped in the jets At this stage the atmosphere becomes oxidizing (air and steam), whereas the temperature remains sufficiently high as shown by melting of metal parts, see Section 3 1 and numerous reports of metal pools on the floor in 305 2)
- Numerical simulation on in-vessel molten corium behavior with external . . .
Natural convection: This is the most critical driving force of the molten corium behavior The large temperature gradient generated by the external reactor vessel cooling in the molten corium leads to turbulent convection Stratification oxide molten metal pool and a lower molten oxide pool
- Numerical investigation of spreading phenomena of molten corium using . . .
Abstract Understanding the behavior of molten corium is crucial for effective heat management and ensuring the integrity of reactor containment during severe nuclear incidents Corium spreading is a complex multi-physics phenomenon influenced by hydrodynamics, heat transfer, and phase change
- Analysis of heat transfer and solidification within CANDU corium
The primary uncertainties in the corium heat transfer and crust formation are associated with the boundary conditions, in particular, the corium top surface emissivity, exterior vessel wall temperature, and the possible presence of an unmelted debris bed at the bottom of the calandria vessel
- Numerical simulation on thermal-hydraulic-mechanical coupling of core . . .
Core corium migration is one of the critical challenges of severe core accidents The lower support plate is a critical load-bearing component within the pressure vessel among core corium migration Investigating the thermal exchange and mechanical failure of the lower support plate during the core migration process holds significant practical
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