Structural integrity confirmation of a once-through steam generator from the viewpoint of flow instability

Journal of Nuclear Science and Technology

Volumn 44, Issue 1, 2007, Pages 64-72

  Kang, Han Ok ^a   Seo, Jae Kwang ^a   Kim, Yong Wan ^a   Yoon, Juhyeon ^a   Kim, Keungkoo ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Dynamic instability; Flow instability; Once through steam generators; Orifice coefficient; Static instability; Structural integrity; Thermal cyclic stress analysis

Indexed keywords

FEEDWATER ANALYSIS; NUCLEAR REACTORS; ORIFICES; STEAM GENERATORS; STRESS ANALYSIS; THERMAL EXPANSION;

DYNAMIC INSTABILITY; FEEDWATER PIPES; FLOW INSTABILITY; ONCE-THROUGH STEAM GENERATORS; ORIFICE COEFFICIENT; STATIC INSTABILITY;

STRUCTURAL INTEGRITY;

EID: 33947138228     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2007.9711257     Document Type: Article

References (18)

1. M. H. Chang et al., “SMART: An advanced small integral PWR for nuclear desalination and power generation,” Proc. Global 99, Int. Conf. Future Nuclear Systems, Jackson Hole, USA, Aug. 29-Sept. 3 (1999).
2. J. W. Seo, H. O. Kang et al., “Insulation performance of a tube-in-tube modular feedwater line for an in-vessel once-through steam generator,” Transaction of the Korean Nuclear Society Autumn Meeting, Busan, Korea, Oct. 27-28 (2005).
3. H. O. Kang et al., Review of Two-phase Instabilities, KAERI/AR-469/97, Korea Atomic Energy Institute (KAERI) (1997).
4. I. Klevtsov, R. Crane, “Random thermal stress oscillations and fatigue life estimation for steam generator tubes,” J. Pressure Vessel Technology, 116, 110 (1994).
5. T. Chiang, D. M. France, T. R. Bump, “Calculation of tube degradation induced by dry-out instability in sodium-heated steam generators,” Nucl. Eng. Des., 41[2], 181 (1977).
6. V. A. Babin et al., Final Report on Problems of Ensuring the Hydrodynamic Stability of the Once-Through Steam Generators in Normal Operating Modes, Afrikantov Experimental Machine Building Design Bureau (OKBM) (2005).
7. J. H. Yoon et al., “Development of a computer code, ONCESG, for the thermal-hydraulic design of a once-through steam generator,” J. Nucl. Sci. Technol., 37[5], 445 (2000).
8. I. E. Idelchik, Handbook of Hydraulic Resistance, 2nd Edition, Hemisphere Publishing Corp. (1986).
9. I. E. Idelchik, The NSSSfor Barge Mounted Small Size CNPP-Steam Generator, SKBK (1997).
10. I. E. Idelchik, Status of Advanced Light Water Reactor Designs 2004, IAEA-TECDOC-1391 (2004).
11. P. A. Petrov, Hydrodynamics of Once-Through Boiler, Gose-nergoizdat (1960).
12. H. O. Kang, J. H. Yoon, “Instability analysis on a once-through steam generator using the drift-flux based 3-equation mixture-fluid model,” The 6th Int. Conf. Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, Oct. 4-8 (2004).
13. N. Zuber, F. W. Staub, “The propagation and the wave form of the vapor volumetric concentration in boiling, forced convection system under oscillatory conditions,” Int. J. Heat Mass Transfer, 9, 871 (1966).
14. J. March-Leuba, J. M. Rey, “Coupled thermohydraulic-neu-tronic instabilities in boiling water nuclear reactors: A review of the state of the art,” Nucl. Eng. Des., 145, 97 (1993).
15. I. Klevtsov, R. Crane, “Random thermal stress oscillations and fatigue life estimation for steam generator tubes,'' Trans. ASME J. Pressure Vessel Technology, 116, 110 (1994).
16. Y. W. Kim, J. I. Kim, M. H. Chang, “An explicit integral expression for the stress intensity factor of a semi-elliptic surface crack subjected to thermal transient loading,” Int. J. Pressure Vessels and Piping, 76, 631 (1999).
17. Y. W. Kim, J. I. Kim, M. H. Chang, ABAQUS/Standard User’s Manual, Hibbit, Karlsson & Sorensen Inc. (2001).
18. Y. W. Kim, J. I. Kim, M. H. Chang, Boiler and Pressure Vessel Code Sec. III, Rules for Construction of Nuclear Power Plant Components, American Society for Mechanical Engineers (ASME) (1998).