DOI QR코드

DOI QR Code

Investigation of Maximum External Pressure of Helically Coiled Steam Generator Tubes with Axial and Circumferential Through-Wall Cracks

축방향 및 원주방향 관통균열이 존재하는 나선형 전열관의 파손 외압 평가

  • Lim, Eun-Mo (Dept. of Mechanical System Design Engineering, Seoul National University of Science and Technology) ;
  • Huh, Nam-Su (Dept. of Mechanical System Design Engineering, Seoul National University of Science and Technology) ;
  • Choi, Shin-Beom (Korea Atomic Energy Research Institute) ;
  • Yu, Je-Yong (Korea Atomic Energy Research Institute) ;
  • Kim, Ji-Ho (Korea Atomic Energy Research Institute) ;
  • Choi, Suhn (Korea Atomic Energy Research Institute)
  • Received : 2013.04.10
  • Accepted : 2013.05.17
  • Published : 2013.06.15

Abstract

Once-through helically coiled steam generator tubes subjected to external pressure are of interest because of their application to advanced small- and medium-sized integral reactors, in which a primary coolant with a relatively higher pressure flows outside the tubes, while secondary water with a relatively lower pressure flows inside the tubes. Another notable point is that the values of the mean radius to thickness ratio of these steam generator tubes are very small, which means that a thick-walled cylinder is employed for these steam generator tubes. In the present paper, the maximum allowable pressure of helically coiled and thick-walled steam generator tubes with through-wall cracks under external pressure is investigated based on a detailed nonlinear three-dimensional finite element analysis. In terms of the crack orientation, either circumferential or axial through-wall cracks are considered. In particular, in order to quantify the effect of the crack location on the maximum external pressure, these cracks are assumed to be located in the intrados, extrados, and flank of helically coiled cylinders. Moreover, an evaluation is also made of how the maximum external pressure is affected by the ovality, which might be inherently induced during the tube coiling process used to fabricate the helically coiled steam generator tubes.

Keywords

References

  1. International Atomic Energy Agency, 2000, Small Power and Heat Generation Systems on the basis of Propulsion and Innovative Reactor Technologies, IAEA-TECDOC-1172.
  2. MacDonald, P. E., Shah, V. N., 1996, Steam Generator Tube Failure, NUREG/CR-6365.
  3. Huh, N. S., Kim, J. M., Chang, Y. S., Kim, Y. J., Hwang, S. S., Kim, J. S., 2007, Elastic-Plastic Fracture Mechanics Assessment for Steam Generator, Fatigue and Fracture of Engineering Materials and Structures, 30 131-142. https://doi.org/10.1111/j.1460-2695.2006.01094.x
  4. Electric Power Research Institute, 1991, Steam Generator Tube Integrity Volume 1: Burst Test Results and Validation of Rupture Criteria (Framatome Data), EPRI NP-6865-L.
  5. Majumdar, S., Kasza, K., Franklin, J., Muscara, J., 2000, Pressure and Leak-Rate Tests and Models for Predicting Failure of Flawed Steam Generator Tubes, USNRC NUREG/CR-6664.
  6. Korea Institute of Nuclear Safety, 2003, Development of Regulatory Technology for Structural Integrity of Components in SMART-P, KINS/HR-553.
  7. American Society of Mechanical Engineers, 2011, Tolerances for Formed or Bent Piping, ASME Boiler and Pressure Vessel Code, Sec. III, Div. 1, NB-4223.
  8. ABAQUS, 2011, ABAQUS/Standard User's Manual Version 6.11-1, Simulia Corp.
  9. Electric Power Research Institute, 1991, Ductile Fracture Handbook, EPRI NP-6301.
  10. Yoo, Y. S., Huh, N. S., Choi, S., Kim, T. W., Kim, J. I., 2010, Collapse Pressure Estimates and The Application of a Partial Safety Factor to Cylinders subjected to External Pressure, Nuclear Engineering and Technology, 42:4 450-459. https://doi.org/10.5516/NET.2010.42.4.450
  11. United States Nuclear Regulatory Commission, 1976, Base for Plugging Degraded PWR Steam Generator Tubes, Regulatory Guide 1.121.
  12. Hill, R., 1950, The Mathematical Theory of Plasticity, Oxford University Press, England.