Heat transfer from fuel rod surface under reactivity-initiated accident conditions; NSRR experiments under varied cooling conditions
反応度事故時の被覆管表面伝熱挙動; 冷却条件をパラメータとしたNSRR実験
宇田川 豊; 杉山 智之; 天谷 政樹
Udagawa, Yutaka; Sugiyama, Tomoyuki; Amaya, Masaki
In order to study the effects of cooling conditions on the boiling heat transfer from the fuel rod surface to the coolant water, RIA-simulating experiments with fresh fuels had been conducted in the nuclear safety research reactor (NSRR) under cooling conditions with subcoolings of $$sim$$ 10 to 80 K, flow velocities of 0 to $$sim$$ 3 m/s, pressures of 0.1 to $$sim$$ 16 MPa. In addition, pre-irradiated fuels had been subjected to the NSRR experiments under cooling conditions with subcoolings of $$sim$$ 80 K, stagnant water, and atmospheric pressure. Out of the NSRR experiments, this report presents the fuel specifications, the test conditions, and the transient records during the pulse operations for the cases that the cladding temperature had been successfully measured. Characteristic parameters such as cladding peak temperatures were extracted from the transient records for summarizing the effects of cooling conditions and pre-irradiation on the heat transfer from the cladding surface.
使用言語 : English
報告書番号 : JAEA-Data/Code 2013-021
ページ数 : 43 Pages
発行年月 : 2014/02
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キーワード : no keyword
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受委託・共同研究相手機関 :
登録番号 : DC20130021
抄録集掲載番号 : 42000261
Accesses  (From Jun. 2, 2014)
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