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Title: Tiểu Ban A: Safety analysis of natural convection heat transfer characteristics in a plate type fuel assembly of Kyoto University Research Reactor under severe accident conditions
Authors: Tu Dau Duc, Daisuke Ito, Yasushi Saito
Keywords: Natural convection heat transfer, Plate-type fuels, LOCA, Transient reactor, KUR
Issue Date: 2017
Publisher: Viện Năng lượng nguyên tử Việt Nam
Abstract: The transient behavior of nuclear fuel during loss of coolant accident (LOCA) must be evaluated not only for power reactors but also for research reactors. Kyoto University Research Reactor (KUR) is a light-water moderated tank-type reactor operated at the rated thermal power of 5 MW and has been widely utilized for a lot of scientific researches. The safety of the plate-type fuels in the KUR has been studied by a reactor system analysis code like RELAP5. However, in the accurate prediction of the natural convection of air at the last state of LOCA, an empirical correlation for natural convection should be selected properly and experimental validations should be performed. In this study, to understand the transient reactor behavior after LOCA, the natural convection heat transfer characteristics were experimentally investigated using a simulated fuel assembly which has the same dimension with the KUR fuels.
Appears in Collections:Hội nghị KHCNHN toàn quốc lần thứ 12

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