Fluid Structure Interaction Analysis on Wall Thinned Pipes


Article Preview

The wall thinning due to erosion, corrosion and flow accelerated corrosion is one of critical issues in nuclear industry. To secure against loss of integrity of pipes with a flaw, ASME Code Section III and Code Case N-597 etc have been used in design and operating stages, respectively. However, despite of their inherent conservatisms, it may reach unanticipated accidents due to degradation at local region. In this paper, a new evaluation scheme is suggested to estimate load-carrying capacities of wall thinned pipes. At first, computational fluid dynamics analyses employing steady-state and incompressible flow are carried out to determine pressure distributions in accordance with conveying fluid. Then, the discriminate pressures are applied as input condition of structural finite element analyses to calculate local stresses at the deepest point. A series of combined analyses were performed for different fluid flow velocities as well as d/t, Rm/t and l/t ratios. The efficiency of proposed scheme was proven from comparison with conventional analyses results and it is recommended to consider the fluid structure interaction effect for exact integrity evaluation.



Key Engineering Materials (Volumes 321-323)

Edited by:

Seung-Seok Lee, Joon Hyun Lee, Ik Keun Park, Sung-Jin Song, Man Yong Choi




Y. S. Chang et al., "Fluid Structure Interaction Analysis on Wall Thinned Pipes", Key Engineering Materials, Vols. 321-323, pp. 670-673, 2006

Online since:

October 2006




[1] S.H. Bush: Journal of Pressure Vessel Technology Vol. 114 (1992), pp.389-395.

[2] Japanese Nuclear and Industrial Safety Subcommittee, Advisory Committee for Natural Resources and Energy: http/www. meti. go. jp/press/0005524/ (2005).

[3] ASME: ASME Boiler and Pressure Vessel Code Section III (1998).

[4] ASME: ASME B&PV Code XI, Division 1, Code Case N-597 (1998).

[5] B. Sreejith, K. Jayaraj, N. Gansesan, C. Padmanabhan, P. Chellapandi and P. Selvaraj: Nuclear Engineering and Design Vol. 227 (2004), pp.313-322.

DOI: https://doi.org/10.1016/j.nucengdes.2003.11.005

[6] C.J. Greenshields, G.P. Venizelos and A. Ivankovic: Journal of Fluids and Structures Vol. 14 (2000), pp.221-234.

[7] W. Erath, B. Nowotny and J. Maetz: Nuclear Engineering and Design Vol. 193 (1999), pp.283-296.

[8] Advanced Technology Engineering Service: GAMBIT 2. X Training Notes (FLUENT, Inc., USA 2005).

[9] Advanced Technology Engineering Service: FLUENT 6. X Training Notes (FLUENT, Inc., USA 2005).

[10] ABAQUS: ABAQUS User's manual Ver. 6. 5 (Hibbitt, Karlsson and Sorensen, Inc., USA 2005).