کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1729543 1521178 2010 11 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Numerical prediction of the fission product plate-out for a VHTR application
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Numerical prediction of the fission product plate-out for a VHTR application
چکیده انگلیسی

In order to identify and quantify the key parameters affecting the predictions of fission product transport and plate-out behavior in the coolant circuits of a very high temperature reactor (VHTR) system, systematic and intensive analyses were performed based on numerical predictions as well as the existing experimental data. For the purpose, the computational module for modeling fission product transport phenomena was developed and incorporated into the system analysis code, GAMMA+ for an integrated analysis. This integration can provide more realistic boundary conditions such as velocity, temperature, etc., during off-normal conditions as well as normal operations in a given VHTR system.The developed module has been applied to predict the fission product transport and plate-out in the experimental loops of VAMPYR-I and OGL-1. A good agreement is found in general between the predictions by the present module and the measured values. The results of the sensitivity analysis have shown that the surface conditions of the coolant circuit can be major source of the uncertainty in the prediction of the plate-out activity of I-131. In the high temperature regions, in particular, it is found that the predicted plate-out activities of I-131 on the oxidized surface result in about 100 times smaller values than those on the unoxidized surface. On the other hand, Cs-137 is found to be less affected by the surface oxidation. It is also confirmed that the diffusion coefficient significantly affects the fission product distribution in the coolant and plate-out activities over the large surface area like heat exchangers.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 37, Issue 4, April 2010, Pages 471–481
نویسندگان
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