After the severe accident inside a nuclear reactor, the IVR (In-vessel retention) management strategy is an effective way to keep the integrity of pressure vessel and reduce risk of radioactive leakage by holding the damaged core materials through External Reactor Vessel Cooling (ERVS). The damaged core materials aggregate in the lower head of pressure vessel and releasing heat to the lower head. Therefore, it is very important to remove heat timely to keep the integrity of pressure vessel by ERVS. The shape of lower head is hemispherical and the local Critical Heat Flux (CHF) of different parts changed with latitude. In this paper, influence of orientation angles, area and length-width ratio on CHF of plate heating surface for saturated pool boiling is investigate experimentally. The results show that CHF increases with increasing orientation angles and decreasing area, meanwhile, length-width ratio has a significantly effect on CHF.
Experimental Investigation on Critical Heat Flux From Downward-Facing Flat Plate for Different Orientation Angles
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Deng, KH, Zhang, Y, Wang, CL, Zhang, YP, Tian, WX, Qiu, SZ, Su, GH, & Wang, Y. "Experimental Investigation on Critical Heat Flux From Downward-Facing Flat Plate for Different Orientation Angles." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06BT08A008. ASME. https://doi.org/10.1115/ICONE26-81844
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