Browse > Article
http://dx.doi.org/10.20466/KPVP.2018.14.2.001

Numerical Analysis on the Characteristics of Supersonic Steam Jet Impingement Load  

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. 1-10 More about this Journal
Abstract
Structures, systems and components of nuclear power plants should be able to maintain safety even in the event of design-basis accidents such as high-energy line breaks. The high-pressure steam jet ejected from the broken pipe may cause damage to the adjacent structures. The ANSI/ANS 58.2 code has been adopted as a technical standard for evaluating the jet impingement load. Recently, the U.S. NRC pointed out the non-conservativeness of the ANSI/ANS 58.2, because it does not take into account the blast wave effect, dynamic behavior of the jet, and oversimplifies the shape and load characteristics of the supersonic steam jet. Therefore, it is necessary to improve the evaluation method for the high-energy line break accident. In order to evaluate the behavior of supersonic steam jet, an appropriate numerical analysis technique considering compressible flow effect is needed. In this study, numerical analysis methodology for evaluating supersonic jet impingement load was developed and verified. In addition, the conservativeness of the ANSI/ANS 58.2 model was investigated using the numerical analysis methodology. It is estimated that the ANSI jet model does not sufficiently reflect the physical behavior of under-expanded supersonic steam jet and evaluates the jet impingement load lower than CFD analysis result at certain positions.
Keywords
Jet Impingement; Under-expanded Jet; Supersonic Jet; High Energy Pipeline; CFD; Compressible Flow;
Citations & Related Records
Times Cited By KSCI : 2  (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 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.
3 Choi, C., Oh, S., Choi, D. K., Kim, W. T., Chang, Y. and Kim, S. H., 2016, "CFD Analysis for Steam Jet Impingement Evaluation," Trans. of the KPVP, Vol. 12, No. 2, pp. 58-65.
4 Wallis, G., 2004, The ANSI/ANS Standard 58.2-1988: Two Phase Jet Model.
5 Ransom., V., 2004, Comments on GSI-191 Models for Debris Generation.
6 USNRC, 2007, "Determination of Rupture Locations and Dynamics Effects Associated with the Postulated Rupture of Piping(Rev.2)," U.S. Nuclear Regulatory Commission, Washington, D.C., NUREG-0800.
7 Kim, H. and Shin, H., 1994, "Numerical Study on Under-Expanded Jets through a Supersonic Nozzle (II)," Trans. of the KSME(B), Vol. 20, No. 6, pp.1994-2004.
8 Krothapalli, A., Hsia, Y. Baganoff, D. and Karamcheti, K., 1986, "The Role of Screech Tones in Mixing of an Underexpanded Rectangular Jet," J. Sound Vib., Vol. 106, No. 1, pp.119-143.   DOI
9 ANSYS, Inc., 2010, ANSYS Fluent User Guide.
10 KAERI, 1993, "A State-of-the-Art Report on Two-Phase Critical Flow Modeling," Korea Atomic Energy Research Institute, KAERI/AR-377/93.
11 Johnson, R. W., 1998, The Handbook of Fluid Dynamics, Springer, pp.17-32 - 17-33.
12 Healzer, J. M. and Elias, E., 1986, "Two-Phase Jet Modeling and Data Comparison," Electric Power Research Institute, Palo Alto, CA, EPRI NP-4362.