Published October 2010 | Version v1
Journal article

Predicting the wall thinning engendered by erosion-corrosion using CFD methodology

  • 1. Department of Engineering and System Science, Institute of Nuclear Engineering and Science, National Tsing Hua University, 101, Sec. 2. Kuang-Fu Rd., Hsingchu 30013, 325 Taiwan (China)

Description

Research highlights: → Resulting in pipe repair, plant shutdown, or even personnel injury, erosion- corrosion is indeed a serious piping degradation mechanism for a nuclear power plant (NPP). → A CFD methodology is proposed to investigate the dependence of wall thinning on the hydrodynamic characteristics within the piping. → Based on the curve describing these relationships of near-wall turbulence kinetic energy and wall thinning, an envelopment model is developed to conservatively predict the amount of local wall thinning around the surface of fitting. - Abstract: Erosion-corrosion (EC) is a serious degradation mechanism of piping, especially for nuclear power plants since it may result in the piping damage, plant shutdown, or personnel injury. The majority of this paper investigates the dependence of wall thinning on the hydrodynamic characteristics using the computational fluid dynamics (CFD) methodology. Four piping systems in a pressurized water reactor (PWR) power plant are selected in this investigation. Based on the plots showing the measured wall thinning with the calculated hydrodynamic parameters, the relationship between them is clearly revealed. Utilizing the characteristics of near-wall turbulence kinetic energy, an envelopment model is proposed herein to conservatively predict the amount of wall thinning distributed on the pipe wall. This estimation model can simply predict the possible distributions of severe EC wear sites and subsequently assist the plant staff to schedule the pipe wall monitoring program in the measured range of pipe wall for the fittings.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.07.031

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.07.031;
PII
S0029-5493(10)00504-2;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
10
Journal Page Range
p. 2836-2841
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
4. international topical meeting on high temperature reactor technology
Acronym
HTR 2008
Dates
28 Sep - 1 Oct 2008
Place
Washington, DC (United States)

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.