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. Noncontact 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 noncontact 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.
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April 2017
Research-Article
A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection
Akinori Tamura,
Akinori Tamura
Hitachi Europe Limited,
7th Floor, Capital House,
25 Chapel Street,
London NW1 5DH, UK
e-mail: akinori.tamura.mt@hitachi.com
7th Floor, Capital House,
25 Chapel Street,
London NW1 5DH, UK
e-mail: akinori.tamura.mt@hitachi.com
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Anthony J. Croxford,
Anthony J. Croxford
Department of Mechanical Engineering,
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: a.j.croxford@bristol.ac.uk
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: a.j.croxford@bristol.ac.uk
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Paul D. Wilcox
Paul D. Wilcox
Department of Mechanical Engineering,
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: p.wilcox@bristol.ac.uk
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: p.wilcox@bristol.ac.uk
Search for other works by this author on:
Akinori Tamura
Hitachi Europe Limited,
7th Floor, Capital House,
25 Chapel Street,
London NW1 5DH, UK
e-mail: akinori.tamura.mt@hitachi.com
7th Floor, Capital House,
25 Chapel Street,
London NW1 5DH, UK
e-mail: akinori.tamura.mt@hitachi.com
Chenghuan Zhong
Anthony J. Croxford
Department of Mechanical Engineering,
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: a.j.croxford@bristol.ac.uk
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: a.j.croxford@bristol.ac.uk
Paul D. Wilcox
Department of Mechanical Engineering,
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: p.wilcox@bristol.ac.uk
University of Bristol,
Queen's Building,
University Walk,
Bristol BS8 1TR, UK
e-mail: p.wilcox@bristol.ac.uk
1Corresponding author.
Manuscript received June 23, 2016; final manuscript received November 30, 2016; published online March 1, 2017. Assoc. Editor: John F. P. de Grosbois.
ASME J of Nuclear Rad Sci. Apr 2017, 3(2): 021003 (9 pages)
Published Online: March 1, 2017
Article history
Received:
June 23, 2016
Revised:
November 30, 2016
Citation
Tamura, A., Zhong, C., Croxford, A. J., and Wilcox, P. D. (March 1, 2017). "A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection." ASME. ASME J of Nuclear Rad Sci. April 2017; 3(2): 021003. https://doi.org/10.1115/1.4035466
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