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Thesis Advisor | Greiner, Miles | |
Author | Alam, Md Hasibul | |
Date Accessioned | 2017-10-23T18:27:55Z | |
Date Available | 2017-10-23T18:27:55Z | |
Date of Issue | 2016 | |
xmlui.metadata.dc.date.submitted | 01/01/2016 | |
Identifier (URI) | http://hdl.handle.net/11714/2117 | |
Description | 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. | |
Item Format | ||
Rights | In Copyright(All Rights Reserved) | |
Subject | Forced Helium Dehydration
| |
Subject | Nuclear Waste Management
| |
Subject | Spent Nuclear Fuel Drying
| |
Title | ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process | |
Type | Thesis | |
xmlui.metadata.dc.date.updated | 2017-10-09T13:28:21Z | |
Rights Holder | Author(s) | |
Committee Member | Hadj-Nacer, Mustafa | |
Committee Member | Tsoulfanidis, Nicholas | |
Department | Mechanical Engineering | |
Degree Level | Master's Degree |