2117 BWR 燃料棒ドライアウト及びリウェッティング現象の高温高圧実機条件下の二相流沸騰可視化試験

概要

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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.
一般社団法人日本機械学会の論文
2003-08-05