著者

森 治嗣 手塚 健一 加賀見 雄一 手塚 英昭

出版者

一般社団法人日本機械学会

雑誌

年次大会講演論文集 : JSME annual meeting

巻号頁・発行日

vol.2003, no.3, pp.187-188, 2003-08-05

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Dry-out and rewetting on fuel rods in a reactor core, possibly observed during the events of pump trip or reactor power increase etc., are significant phenomena from the viewpoints of securing the integrity of a fuel rod and safety evaluation on MCPR in the design. The two-phase flow boiling visualization experiments of dry-out and rewetting processes by a high-speed digital movie were successfully carried out under BWR rated-operating condition of ∿7MPa and ∿286℃ in the present work; on the other hand, these visualization tests could be found only under the atmospheric pressure conditions so far. The tests were carried out using the thermal-hydraulic experimental loop of Tokyo Electric Power Co., Inc. (TEPCO), which enables us to directly observe the two-phase flow boiling, dry-out and rewetting phenomena under the BWR rated-operating conditions of ∿7MPa and ∿286℃. The observations by a high-speed digital movie, measurements of void fraction increase by optical-fiber void probes and rods' surface temperature soaring and steep diving by thermocouples brought us incontrovertible evidences of the occurrence of rewetting just after dry-out in transients.