Experimental investigation of flow accelerated corrosion under two-phase flow conditions

  • Wael H. Ahmed*
  • , Mufatiu M. Bello
  • , Meamer El Nakla
  • , Abdelsalam Al Sarkhi
  • , Hassan M. Badr
  • *Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

41 Scopus citations

Abstract

The main objective of this paper is to experimentally study the effect of two-phase flow on flow-accelerated corrosion (FAC) downstream an orifice. FAC is a major safety and reliability issue affecting carbon-steel piping in nuclear and fossil power plants. This is because of its pipe wall wearing and thinning effects that could lead to sudden and sometimes catastrophic failures, as well as a huge economic loss. In the present study, FAC wear of carbon-steel piping was simulated experimentally by circulating air-water mixtures through hydrocal (CaSO4·1/2H2O) test sections at liquid superficial Reynolds number, Re = 20,000, and different air mass flow rates. Experiments were performed for a test section with different orifice to pipe diameter ratios (do/D = 0.25, 0.5 and 0.74). The observed flow patterns were compared with the available flow pattern maps. Surface wear patterns downstream the orifices were also analyzed. The maximum FAC wear was found to occur at approximately 2-5 pipe diameters downstream of the orifice. The obtained results were found to be consistent with those from a single-phase flow study reported earlier. Moreover, FAC was found to depend on the relative values of the mixture mass quality and the volumetric void fraction. Lower values of FAC wear rate were obtained for higher values of mass quality. A modified correlation is developed in order to predict FAC wear rate downstream of the pipe-restricting orifice with an average RMS accuracy of ±10%. However, the location of maximum wear rate is well predicted. The current study is considered as an integrated effort to develop guidelines to FAC engineers in power plants in order to prepare more reliable plant inspection scope.

Original languageEnglish
Pages (from-to)34-43
Number of pages10
JournalNuclear Engineering and Design
Volume267
DOIs
StatePublished - Feb 2014

Bibliographical note

Funding Information:
The authors would like to thank King Abdulaziz City for Science and Technology (KACST) for funding this work under the National Science Technology Plan (NSTIP) grant no. 11-ADV1619-04 . Also, the support provided by the Deanship of Scientific Research (DSR) at King Fahd University of Petroleum & Minerals (KFUPM) is gratefully acknowledged. The authors thank Mr. Malik for performing SME tests, and to Mr. Ahmed Abdel Rehim for fabricating the hydrocal test sections.

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • General Materials Science
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

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