Dry-out and rewetting phenomenon may occur on a fuel rod surface during anticipated operational occurrences (AOOs) for a boiling water reactor (BWR). The conventional rewetting model included in the current system code tends to underestimate the rewetting propagation velocity due to the absence of an appropriate precursory cooling model. The present research aims at the development of a mechanistic model for the precursory cooling in the annular mist flow regime typical of AOO and anticipated transition without scrum (ATWS). Rewetting experiments were carried out using a single heater rod in the circular glass pipe with air-water flow at atmospheric pressure to visualize the rewetting behavior and obtain mechanistic understanding on the phenomena. This paper summarizes the experimental results and discusses the liquid film flow characteristics including roll wave formation and spattering at the rewetting front.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5149-4
PROCEEDINGS PAPER
On the Liquid Film Flow Characteristics During the Rewetting in the Single Rod Air-Water System
Yuki Wada,
Yuki Wada
Japan Atomic Energy Agency, Tokai-mura, Japan
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Dan Le,
Dan Le
Japan Atomic Energy Agency, Tokai-mura, Japan
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Akira Satou,
Akira Satou
Japan Atomic Energy Agency, Tokai-mura, Japan
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Yasuteru Sibamoto,
Yasuteru Sibamoto
Japan Atomic Energy Agency, Tokai-mura, Japan
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Taisuke Yonomoto
Taisuke Yonomoto
Japan Atomic Energy Agency, Tokai-mura, Japan
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Yuki Wada
Japan Atomic Energy Agency, Tokai-mura, Japan
Dan Le
Japan Atomic Energy Agency, Tokai-mura, Japan
Akira Satou
Japan Atomic Energy Agency, Tokai-mura, Japan
Yasuteru Sibamoto
Japan Atomic Energy Agency, Tokai-mura, Japan
Taisuke Yonomoto
Japan Atomic Energy Agency, Tokai-mura, Japan
Paper No:
ICONE26-82491, V06BT08A061; 10 pages
Published Online:
October 24, 2018
Citation
Wada, Y, Le, D, Satou, A, Sibamoto, Y, & Yonomoto, T. "On the Liquid Film Flow Characteristics During the Rewetting in the Single Rod Air-Water System." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06BT08A061. ASME. https://doi.org/10.1115/ICONE26-82491
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