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http://dx.doi.org/10.20466/KPVP.2018.14.2.077

Numerical Analysis on the Transient Load Characteristics of Supersonic Steam Impinging Jet using LES Turbulence Model  

Oh, Se-Hong ((주)엘쏠텍)
Choi, Dae Kyung ((주)엘쏠텍)
Park, Won Man ((주)엘쏠텍)
Kim, Won Tae ((주)아리텍)
Chang, Yoon-Suk (경희대학교 원자력공학과)
Choi, Choengryul ((주)엘쏠텍)
Publication Information
Transactions of the Korean Society of Pressure Vessels and Piping / v.14, no.2, 2018 , pp. 77-87 More about this Journal
Abstract
In the case of high-energy line breaks in nuclear power plants, supersonic steam jet is formed due to the rapid depressurization. The steam jet can cause impingement load on the adjacent structures, piping systems and components. In order to secure the design integrity of the nuclear power plant, it is necessary to evaluate the load characteristics of the steam jet generated by high-energy pipe rupture. In the design process of nuclear power plant, jet impingement load evaluation was usually performed based on ANSI/ANS 58.2. However, U.S. NRC recently pointed out that ANSI/ANS 58.2 oversimplifies the jet behavior and that some assumptions are non-conservative. In addition, it is recommended that dynamic analysis techniques should be applied to consider transient load characteristics. Therefore, it is necessary to establish an evaluation methodology that can analyze the dynamic load characteristics of steam jet ejected when high energy pipe breaks. This research group has developed and validated the CFD analysis methodology to evaluate the transient behavior of supersonic impinging jet in the previous study. In this study, numerical study on the transient load characteristics of supersonic steam jet impingement was carried out and amplitude and frequency analysis of transient jet load was performed.
Keywords
Jet Impingement; Transient Load; Supersonic Jet; High Energy Pipeline; CFD; LES; Compressible Flow;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 ANS, 1998, "Design Basis for Protection of Light Water Nuclear Power Plants against the Effects of Postulated Pipe Rupture," ANSI/ANS-58.2-1988(W1998).
2 USNRC, 2007, "Determination of Rupture Locations and Dynamics Effects Associated with the Postulated Rupture of Piping(Rev.2)," U.S. Nuclear Regulatory Commission, Washington, DC, NUREG-0800.
3 Wallis, G., 2004, "The ANSI/ANS Standard 58.2-1988: Two Phase Jet Model".
4 Ransom., V., 2004, "Comments on GSI-191 Models for Debris Generation".
5 Oh, S., Choi, D. K., Kim, W. T., Chang, Y. and Choi, C., 2017, "Numerical Analysis on Feedback Mechanism of Supersonic Impinging Jet using LES," Trans. of the KPVP, Vol. 13, No. 2, pp. 51-59.
6 Johnson, R. W., 1998, "The Handbook of Fluid Dynamics," Springer, pp.17-32-17-33.
7 ANSYS, Inc., 2010, "ANSYS Fluent User Guide".