Title of article
Modeling of heat and mass transfer in accelerator targets during postulated accidents
Author/Authors
Unal، Cetin نويسنده , , Bohl، William R. نويسنده , , Pasamehmetoglu، Kemal O. نويسنده ,
Issue Information
دوهفته نامه با شماره پیاپی سال 2000
Pages
-184
From page
185
To page
0
Abstract
The modeling of thermal-chemical behavior of targets used in accelerator applications is an important part of safely analysis. Tungsten is considered as a target material to produce tritium in a linear proton accelerator. The prediction of the chemical reactivity of tungsten in a steam flow at high temperatures is the most important part of a safety analysis of target design. The oxidation and volatilization of tungsten in steam at high temperatures is a complex phenomenon that involves various mechanisms (depending on the temperature), steam pressure, and steam velocity. A simple diffusion model that considers chemical equilibrium at the reaction interface and effective diffusion thickness, including the boundary and oxide layers, is proposed for predicting the volatilization rate. The proposed simple model predicts the available data reasonably well. The proposed model is implemented into a computer program that is developed to predict the radiological releases during postulated loss-of-coolant accidents (LOCAs). The computer program models heat production, heat transfer, and oxidation reactions in the multiple radiation enclosures representing the accelerator target elements. It treats each element of the radiation enclosures as a lumped control volume, or heat structure. Each heat structure may generate or lose heat by conduction, convection, or radiation and is subject to mass loss as a result of oxidation, melting, and volatilization. Postulated beyond-designbasis LOCAs are simulated with this computer program for the accelerator-production-of-tritium target. Sample calculations demonstrate oxidation/volatilization model capabilities and sensitivity to the assumptions selected.
Keywords
Superelement , Finite element method , stress-strain state calculation
Journal title
Nuclear Engineering and Design
Serial Year
2000
Journal title
Nuclear Engineering and Design
Record number
13748
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