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AbstractAbstract
[en] An advanced loop-type sodium-cooled fast reactor has been developed by the Japan Atomic Energy Agency. The upper internal structure (UIS) above the core is a key component where control rod guide tubes are housed. A radial slit is set in the UIS to simplify the fuel-handling system and to reduce the reactor vessel diameter. A high-velocity upward flow is formed in the UIS slit. This slit jet influences thermal hydraulic issues in the reactor vessel. A water experiment was carried out to understand the flow field in the UIS, which is composed of the control rod guide tubes and several horizontal perforated plates with a slit. A refractive index matching method was applied to visualize the flow in such a complex geometry. Velocity measurement using particle image velocimetry showed that the velocity in the UIS slit was accelerated by the multiple slits and kept at a high value at the mid-height of the reactor upper plenum. A numerical simulation was carried out for this complex geometry of the UIS to obtain an adequate simulation method. A comparison between the experimental and analytical velocity profiles showed that the numerical simulation is highly applicable. (author)
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Source
NTHAS6: 6. Japan-Korea symposium on nuclear thermal hydraulics and safety; Nago, Okinawa (Japan); 24-27 Nov 2008; Available from http://dx.doi.org/10.3327/jnst.47.810; 10 refs., 17 figs., 2 tabs.
Record Type
Journal Article
Literature Type
Conference
Journal
Journal of Nuclear Science and Technology (Tokyo); ISSN 0022-3131;
; v. 47(9); p. 810-819

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