Comparison of Two-Phase Critical Flow Models for Estimation of Leak Flow Rate through Cracks
The estimation of leak flow rates through narrow cracks in structures is of importance for nuclear reactor safety, since the leak flow could be detected before occurrence of loss-of-coolant accidents. The two-phase critical leak flow rates are calculated using the system analysis code, and two representative non-homogeneous critical flow models, Henry-Fauske model and Ransom-Trapp model, are compared. The pressure decrease and vapor generation in the crack, and the leak flow rates are found to be larger for the Henry-Fauske model. It is shown that the leak flow rates are not affected by the structural temperature, but affected largely by the roughness of crack surface.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.3566405Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 716
 T. Isozaki, I. Hashiguchi, K. Kato, S. Miyazono, Estimation of Leak Rates by EPRI Code, JAERI-M 87-121, Japan Atomic Energy Research Institute, 1987.
 N. Tyujyo, K. Shibata, T. Isozaki, K. Onizawa, Estimation of Leak Rates through a Through-Wall Cracked Pipes using Moody’s Critical Flow Model, JAERI-M 88-039, Japan Atomic Energy Research Institute, 1988.
 H. Shinokawa, K. Shibata, T. Isozaki, Development of Leak Analysis Programs from Through-Wall-Crack, JAERI-M 90-050, Japan Atomic Energy Research Institute, 1990.
 D.S. Kupperman, S.H. Sheen, W.J. Shack, D.R. Diercks, P. Krishnaswamy, D. Rudland, G.M. Wilkowski, Barrier Integrity Research Program Final Report, NUREG/CR-6861, 2004, U.S. Nuclear Regulatory Commission
 E. Elias, G.S. Lellouche, Two-Phase Critical Flow, International Journal of Multiphase Flow, 20, 1994, pp. 91-168
 Nuclear Safety Analysis Division, RELAP5/MOD3.3 Code Manual, Information Systems Laboratories, Inc. , 2003.
 L. Sokolowski, T. Kozlowski, Assessment of Two-Phase Critical Flow Models Performance in RELAP5 and TRACE against Marviken Critical Flow Tests, NUREG/IA-0401, 2011, U.S. Nuclear Regulatory Commission.
 R.E. Henry, H.K. Fauske, The Two-Phase Critical Flow of One-Component Mixtures in Nozzles, Orifices, and Short Tubes, Journal of Heat Transfer. 93, 1971, pp. 179-187
 Y.S. Kim, Critical Flow Maps using an Extended Henry-Fauske Model, Annals Nuclear Engineering, 75, 2015, pp. 516-520.