ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process
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Authors
Alam, Md Hasibul
Issue Date
2016
Type
Thesis
Language
Keywords
Forced Helium Dehydration , Nuclear Waste Management , Spent Nuclear Fuel Drying
Alternative Title
Abstract
This thesis describes the development and design of simulation model in “ANSYS FLUENT” for Spent Nuclear Fuel dehydration process by “Forced Helium Dehydration” [13] method [28]. The simulation model was developed using the computational fluid dynamics software “FLUENT” [28]. After defueling a nuclear reactor, the fuel rods are kept underwater. Later they are put into a transfer cask. The fuel rods have to be stored in dry condition for long term storage. “Forced helium dehydration” [13] process uses dry helium gas flow to remove water content from the transfer cask. The mass transfer occurs due to diffusion-advection and evaporation-boiling. There are several evaporation and boiling methods available built in “FLUENT” [28]. So, an optimized method was chosen which was used for simulation of mass transfer in the “Forced Helium Dehydration” [13] process. The method was verified in a two dimensional model, then applied to a three dimensional model. The spent nuclear fuel rods can be arranged in different arrays inside the canister. For our simulation, we used a 7 x 7 array of spent nuclear fuel rods.
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In Copyright(All Rights Reserved)