• Title/Summary/Keyword: Nuclear technique

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Simulation Based Investigation of Focusing Phased Array Ultrasound in Dissimilar Metal Welds

  • Kim, Hun-Hee;Kim, Hak-Joon;Song, Sung-Jin;Kim, Kyung-Cho;Kim, Yong-Buem
    • Nuclear Engineering and Technology
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    • v.48 no.1
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    • pp.228-235
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    • 2016

  • Flaws at dissimilar metal welds (DMWs), such as reactor coolant systems components, Control Rod Drive Mechanism (CRDM), Bottom Mounted Instrumentation (BMI) etc., in nuclear power plants have been found. Notably, primary water stress corrosion cracking (PWSCC) in the DMWs could cause significant reliability problems at nuclear power plants. Therefore, phased array ultrasound is widely used for inspecting surface break cracks and stress corrosion cracks in DMWs. However, inspection of DMWs using phased array ultrasound has a relatively low probability of detection of cracks, because the crystalline structure of welds causes distortion and splitting of the ultrasonic beams which propagates anisotropic medium. Therefore, advanced evaluation techniques of phased array ultrasound are needed for improvement in the probability of detection of flaws in DMWs. Thus, in this study, an investigation of focusing and steering phased array ultrasound in DMWs was carried out using a time reversal technique, and an adaptive focusing technique based on finite element method (FEM) simulation. Also, evaluation of focusing performance of three different focusing techniques was performed by comparing amplitude of phased array ultrasonic signals scattered from the targeted flaw with three different time delays.

  • https://doi.org/10.1016/j.net.2015.10.011 인용 PDF KSCI

Enhancement of Downward-Facing Saturated Boiling Heat Transfer by the Cold Spray Technique

  • Sohag, Faruk A.;Beck, Faith R.;Mohanta, Lokanath;Cheung, Fan-Bill;Segall, Albert E.;Eden, Timothy J.;Potter, John K.
    • Nuclear Engineering and Technology
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    • v.49 no.1
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    • pp.124-133
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    • 2017

  • In-vessel retention by passive external reactor vessel cooling under severe accident conditions is a viable approach for retention of radioactive core melt within the reactor vessel. In this study, a new and versatile coating technique known as "cold spray" that can readily be applied to operating and advanced reactors was developed to form a microporous coating on the outer surface of a simulated reactor lower head. Quenching experiments were performed under simulated in-vessel retention by passive external reactor vessel cooling conditions using test vessels with and without cold spray coatings. Quantitative measurements show that for all angular locations on the vessel outer surface, the local critical heat flux (CHF) values for the coated vessel were consistently higher than the corresponding CHF values for the bare vessel. However, it was also observed for both coated and uncoated surfaces that the local rate of boiling and local CHF limit vary appreciably along the outer surface of the test vessel. Nonetheless, results of this intriguing study clearly show that the use of cold spray coatings could enhance the local CHF limit for downward-facing boiling by > 88%.

  • https://doi.org/10.1016/j.net.2016.08.005 인용 PDF KSCI