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Numerical Analysis of Self-wastage Phenomena Caused by Sodium-Water Reaction in Sodium-Cooled Fast Reactor throuah Simulant Experiment
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作者 Sunghyon Jang Takashi Takata Akira Yamguchi 《Journal of Energy and Power Engineering》 2015年第6期539-547,共9页
A water leakage on the surface of heat transfer tube in a steam generator of sodium-cooled fast reactor causes SWR (sodium-water reaction). The SWR damages the leak surface and gives rise to the leak enlargement. Mo... A water leakage on the surface of heat transfer tube in a steam generator of sodium-cooled fast reactor causes SWR (sodium-water reaction). The SWR damages the leak surface and gives rise to the leak enlargement. Most of initial leakage starts from micro leak (less than 0.5 g/s). However, the leak rate increases more than two orders of magnitude and the resultant leak damages surrounding heat transfer tubes and it brings secondary failure of the heat transfer tube. Evaluation of the leak enlargement is necessary to assess the leak rate increase, so that evaluate the possibility of secondary failure. In this study, a simulant experiment, which uses neutralization reaction, is proposed to reproduce the leak enlargement. To examine the feasibility of the experiment, numerical simulations are carried out. From the result, a funnel-shaped nozzle enlargement is observed and the shape similar to the shape of the enlarged nozzle from the SWAT (sodium-water reaction test loop) experiment. 展开更多
关键词 Sodium-cooled fast reactor self-wastage phenomena sodium-water reaction simulant experiment CFD (computationalfluid dyanamics).
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