Fuel debris retrieval in atmospheric conditions is proposed as one candidate in the Fukushima Daiichi NPS since it can suppress generation of the contaminated water. However, there are unknowns and uncertainties to evaluate the air cooling performance of the fuel debris. Solving the problems, we have been developing the air-cooling analysis method for accumulated debris in the pedestal. A numerical simulation code JUPITER, which is based on a CFD technics and treats a multi-phase, multi-component thermal-hydraulics, is used as the basis of the method. We preliminary evaluated the effect of debris shapes and heat source conditions on free convection and heat transfer in the simplified structure of the pedestal region using the JUPITER. As a result, it was confirmed that the flow pattern of the free convection in the pedestal clearly differs with debris shapes and a correlation exists between the temperature distribution and the velocity fluctuation around the debris surface.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5784-7
PROCEEDINGS PAPER
Development of Numerical Simulation Method to Evaluate Heat Transfer Performance of Air Around Fuel Debris: Part 1 — Effect of the Debris Shape Available to Purchase
Susumu Yamashita,
Susumu Yamashita
Japan Atomic Energy Agency, Tokai-mura, Japan
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Shinichiro Uesawa,
Shinichiro Uesawa
Japan Atomic Energy Agency, Tokai-mura, Japan
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Hiroyuki Yoshida
Hiroyuki Yoshida
Japan Atomic Energy Agency, Tokai-mura, Japan
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Susumu Yamashita
Japan Atomic Energy Agency, Tokai-mura, Japan
Shinichiro Uesawa
Japan Atomic Energy Agency, Tokai-mura, Japan
Hiroyuki Yoshida
Japan Atomic Energy Agency, Tokai-mura, Japan
Paper No:
ICONE25-67516, V006T08A096; 8 pages
Published Online:
October 17, 2017
Citation
Yamashita, S, Uesawa, S, & Yoshida, H. "Development of Numerical Simulation Method to Evaluate Heat Transfer Performance of Air Around Fuel Debris: Part 1 — Effect of the Debris Shape." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A096. ASME. https://doi.org/10.1115/ICONE25-67516
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