A code was developed in this study to predict the leakage of the leak before break (LBB). Various stagnation conditions were considered, including the subcooled water, the two-phase fluid and the overheated steam. Moreover, both the critical and noncritical flow was studied. The Henry-Fauske critical flow model was revised by a new phase transition point and the pressure drop due to friction and turns were modified. The code was verified by the comparison with the experimental data on the leakage of conventional pipes, artificial cracks and naturally occurring cracks, which shows a good agreement and this code has a higher precision than the existing codes. The influence of crack morphologies on LBB leakage was discussed, including the local roughness, the global roughness, the crack open displacement (COD) and the number of the corners. Besides, the dependence of the LBB leakage on stagnation enthalpy and back pressure was also investigated.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4591-2
PROCEEDINGS PAPER
A Prediction of the Leakage Through Cracks for Leak Before Break
Jing Zhang,
Jing Zhang
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Yingwei Wu,
Yingwei Wu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Lei Ding,
Lei Ding
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Hongwei Qiao,
Hongwei Qiao
Nuclear Power Institute of China Second Sub-Institute, Chengdu, Sichuan, China
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Pengzhou Li,
Pengzhou Li
Nuclear Power Institute of China Second Sub-Institute, Chengdu, Sichuan, China
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Guanghui Su,
Guanghui Su
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Suizheng Qiu,
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Wenxi Tian
Wenxi Tian
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Jing Zhang
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Yingwei Wu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Lei Ding
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Hongwei Qiao
Nuclear Power Institute of China Second Sub-Institute, Chengdu, Sichuan, China
Pengzhou Li
Nuclear Power Institute of China Second Sub-Institute, Chengdu, Sichuan, China
Guanghui Su
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Wenxi Tian
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Paper No:
ICONE22-30708, V02BT09A018; 9 pages
Published Online:
November 17, 2014
Citation
Zhang, J, Wu, Y, Ding, L, Qiao, H, Li, P, Su, G, Qiu, S, & Tian, W. "A Prediction of the Leakage Through Cracks for Leak Before Break." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 2B: Thermal Hydraulics. Prague, Czech Republic. July 7–11, 2014. V02BT09A018. ASME. https://doi.org/10.1115/ICONE22-30708
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