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http://dx.doi.org/10.5293/kfma.2013.16.4.035

Numerical Study of the Averaging BDFT(bidirectional flow tube) Flow Meter on the Applicability in the Fouling Condition  

Park, JongPil (Pusan National University, School of Mechanical Engineering, Energy Systems Major)
Jeong, JiHwan (Pusan National University, School of Mechanical Engineering, Energy Systems Major)
Kang, KyongHo (Korea Atomic Energy Research Institute, Nuclear Safety Research Department)
Baek, WonPil (Korea Atomic Energy Research Institute, Nuclear Safety Research Department)
Yun, ByongJo (Pusan National University, School of Mechanical Engineering, Nuclear Systems Major)
Publication Information
The KSFM Journal of Fluid Machinery / v.16, no.4, 2013 , pp. 35-43 More about this Journal
Abstract
Most of the nuclear power plants(NPPs) adopts pressure difference type flow meters such as venturi and orifice meters for the measurement of feedwater flow rates to calculate reactor thermal power. However, corrosion products in the feedwater deposits on the flow meter by fouling as operating time goes. These effects lead to severe errors in the flow indication and then determination of reactor thermal power. The averaging BDFT, which has developed by Yun et al., has a potentiality to minimize this problem thanks to its inherent measurement principle. Therefore, it is expected that the averaging BDFT can replace the venturi meter for the feedwater pipe of steam generator of NPPs. The present work compares the amplification factor, K, based on CFD calculation against the K obtained from experiments in order to confirm whether a commercial CFD code can be applicable to the evaluation of characteristic for the averaging BDFT. In addition to this, the simulations to take into account of fouling effect are also carried out by rough wall option. The results show that the averaging BDFT is a promising flow meter for the accurate measurement of flow rates in the fouling condition of the NPPs.
Keywords
Amplification factor; Averaging bidirectional flow tube; Computational fluid dynamics; Nuclear power plant; Fouling;
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