In relation to development of the flow regime criteria for rod bundles, this paper provides an experimental flow regime map and compares the experimental map with the existing flow regime transition criteria for vertical rod bundles so far. An experiment of vertical adiabatic air-water flow was conducted under an atmosphere pressure conditions. The experiment facility was composed of 5×5 rod arranged on a square pitch in a square shell with 9.5 mm outside diameter and 12.6 mm pitch. A total of 242 data sets were acquired consisting of superficial gas flow rates, 0.02–8.69 m/s, and superficial liquid flow rates, 0.02–2.13 m/s. A new flow regime map was obtained and the flow regime transition model for rod bundles was validated by the measured flow regime map. A fairly good agreement with some discrepancies has been obtained between the existing flow regime transition criteria and measured flow regime maps for rod bundles.
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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
Experimental Study of Flow Regime Map in 5×5 Rod Bundle
Quanyao Ren,
Quanyao Ren
Chongqing University, Chongqing, China
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Liangming Pan,
Liangming Pan
Chongqing University, Chongqing, China
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Takashi Hibiki,
Takashi Hibiki
Purdue University, West Lafayette, IN
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Wenxiong Zhou,
Wenxiong Zhou
Chongqing University, Chongqing, China
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Tingpu Ye
Tingpu Ye
Chongqing University, Chongqing, China
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Hang Liu
Chongqing University, Chongqing, China
Quanyao Ren
Chongqing University, Chongqing, China
Liangming Pan
Chongqing University, Chongqing, China
Takashi Hibiki
Purdue University, West Lafayette, IN
Wenxiong Zhou
Chongqing University, Chongqing, China
Tingpu Ye
Chongqing University, Chongqing, China
Paper No:
ICONE25-67307, V006T08A089; 8 pages
Published Online:
October 17, 2017
Citation
Liu, H, Ren, Q, Pan, L, Hibiki, T, Zhou, W, & Ye, T. "Experimental Study of Flow Regime Map in 5×5 Rod Bundle." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A089. ASME. https://doi.org/10.1115/ICONE25-67307
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