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A Feasibility Study of Non-Contact Ultrasonic Sensor for Nuclear Power Plant Inspection

[+] Author and Article Information
Akinori Tamura

Hitachi Europe Limited 7th Floor, Capital House, 25 Chapel Street, London, NW1 5DH, United Kingdom
akinori.tamura.mt@hitachi.com

Chenghuan Zhong

Inductosense Ltd Engine Shed, Station Approach, Bristol, BS1 6QH
bamboo@inductosense.com

Anthony J Croxford

Department of Mechanical Engineering, University of Bristol Queen's Building, University Walk, Bristol, BS8 1TR, United Kingdom
a.j.croxford@bristol.ac.uk

Paul D Wilcox

Department of Mechanical Engineering, University of Bristol Queen's Building, University Walk, Bristol, BS8 1TR, United Kingdom
p.wilcox@bristol.ac.uk

1Corresponding author.

ASME doi:10.1115/1.4035466 History: Received June 23, 2016; Revised November 30, 2016

Abstract

A pipe-wall thinning measurement is a key inspection to ensure the integrity of the piping system in nuclear power plants. To monitor the integrity of the piping system, a number of ultrasonic thickness measurements are manually performed during the outage of the nuclear power plant. Since most of the pipes are covered with an insulator, removing the insulator is necessary for the ultrasonic thickness measurement. Non-contact ultrasonic sensors enable ultrasonic thickness inspection without removing the insulator. This leads to reduction of the inspection time and reduced radiation exposure of the inspector. The inductively coupled transducer system (ICTS) is a non-contact ultrasonic sensor system which uses electromagnetic induction between coils to drive an installed transducer. In this study, we investigated the applicability of an innovative ICTS developed at the University of Bristol to nuclear power plant inspection, particularly pipe-wall thinning inspection. The following experiments were performed using ICTS: thickness measurement performance, the effect of the coil separation, the effect of the insulator, the effect of different inspection materials, the radiation tolerance, and the measurement accuracy of wastage defects. These initial experimental results showed that the ICTS has the possibility to enable wall-thinning inspection in nuclear power plants without removing the insulator. Future work will address the issue of measuring wall-thinning in more complex pipework geometries and at elevated temperatures.

Copyright (c) 2016 by ASME
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