International Journal of Scientific Research and Engineering Development

International Journal of Scientific Research and Engineering Development

( International Peer Reviewed Open Access Journal ) ISSN [ Online ] : 2581 - 7175

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Mie Model of Radiation Heat Transferin Isothermal Spherical Medium

     International Journal of Scientific Research and Engineering Development (IJSRED)

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 Published Issue : Volume-3 Issue-5
 Year of Publication : 2020
 Unique Identification Number : IJSRED-V3I5P54
 Authors : Hamza Mohamed
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Abstract :

In certain extremely low probability, severe accident scenarios which have been postulated for liquid metal cooled fast reactors,large bubble cavities containing fuel vapor and fission products transit a layer of coolant and release this material to the cover gas thereby presenting a contribution to an accident-specific source term [5].Mie model in radiation heat transfer has been investigated to analysis and interpret the experiments that conducted during 1980’s for oxide UO2 fueled reactors in Fuel Aerosol Simulant Test (FAST) facility at Oak Ridge National Laboratory (ORNL).These analyses are applied to estimate the bubble collapse of Liquid Metal reactors (LMR’s) during a hypothetical core disruptive accident (HCDA).InMie scattering model the particle size was 0.07 µm [6]. The scattering coefficient of UO2 particles (σ = 1.24 m-1 ), was calculated by using Mie theory,at the same number of stable nuclei’s N ( 2.9 E15 nuclei/m3) that resulted from theabsorbed coefficientk = 0.082 m-1[7].P1 approximation method was used to solve the radiative heat transfer equation (RTE) in spherical coordinates of participating medium confined between the two concentric spheres.The surfaces of the spheres are assumed to be gray, diffusely emitting and diffusely reflecting boundaries, and an isothermal boundary conditions were assumed at these surfaces.Marsak’s boundary condition was to computed, the net radiative heat flux q(τ), and the incident radiation G(τ), to analyze and interpret the CVD experiments data that were conducted in the FAST facility at ORNL [8] and Fast Flux Test Facility reactor (FFTF) in Argonne National Laboratory ANL.The conclude that extracted from this study is greater margin of safety when the bubble rising time is greater than the bubble collapse time since the bubble collapses (UO2 condenses) before it can reach the top of the vessel therefore there is less chance of release of aerosol as in Oak Ridge National Laboratory (ORNL) FAST experiments and Argonne National Laboratory (FFTF) reactor.