Flow and mass transfer downstream of an orifice under flow accelerated corrosion conditions

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

Research output: Contribution to journalArticlepeer-review

92 Scopus citations

Abstract

Local flow parameters play an important role in characterizing flow accelerated corrosion (FAC) downstream of sudden area change in power plant piping systems. Accurate prediction of the highest FAC wear rate locations enables the mitigation of sudden and catastrophic failures, and the improvement of the plant capacity factor. The objective of the present study is to evaluate the effect of the local flow and mass transfer parameters on flow accelerated corrosion downstream of an orifice. In the present study, orifice to pipe diameter ratios of 0.25, 0.5 and 0.74 were investigated numerically by solving the continuity and momentum equations at Reynolds number of Re = 20,000. Laboratory experiments, using test sections made of hydrocal (CaSO 4·1/2H 2O) were carried out in order to determine the surface wear pattern and validate the present numerical results. The numerical results were compared to the plants data as well as to the present experiments. The maximum mass transfer coefficient found to occur at approximately 2-3 pipe diameters downstream of the orifice. This location was also found to correspond to the location of elevated turbulent kinetic energy generated within the flow separation vortices downstream of the orifice. The FAC wear rates were correlated with the turbulence kinetic energy and wall mass transfer in terms of Sherwood number. The current study found to offer very useful information for FAC engineers for better preparation of plant inspection scope.

Original languageEnglish
Pages (from-to)52-67
Number of pages16
JournalNuclear Engineering and Design
Volume252
DOIs
StatePublished - Nov 2012

Bibliographical note

Funding Information:
The support provided by the Deanship of Scientific Research (DSR) at King Fahd University of Petroleum & Minerals (KFUPM) for funding this work through the project No. IN090038, is gratefully acknowledged. The authors thank Dr. Mohamed El-Gammal and Dr. Chan Ching for their valuable input into this work. Special thanks to Mr. Hassan Iqbal for performing the laser scanning, at the Rapid Prototyping Laboratory, and to Mr. Ahmed Abdel Rehim for fabricating the hydrocal test sections.

ASJC Scopus subject areas

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

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