scholarly journals Development of Wall-Thinning Evaluation Procedure for Nuclear Power Plant Piping—Part 1: Quantification of Thickness Measurement Deviation

2016 ◽  
Vol 48 (3) ◽  
pp. 820-830 ◽  
Author(s):  
Hun Yun ◽  
Seung-Jae Moon ◽  
Young-Jin Oh
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Thickness Measurement ◽  
Evaluation Procedure ◽  
Wall Thinning ◽  
Measurement Deviation

A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection

2017 ◽  
Vol 3 (2) ◽  
Author(s):  
Akinori Tamura ◽  
Chenghuan Zhong ◽  
Anthony J. Croxford ◽  
Paul D. Wilcox
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Pipe Wall ◽  
Thickness Measurement ◽  
Piping System ◽  
Wall Thinning ◽  
Plant Inspection ◽  
Ultrasonic Thickness

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.

Diagnostics of Nuclear Power Plant Components Due to Thickness Measurement by Using Digital Radiography

2010 ◽  
Author(s):  
Masahito Mochizuki ◽  
Satoshi Kanno ◽  
Shunichi Shimizu ◽  
Yuichi Daitou
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Digital Radiography ◽  
Nuclear Power ◽  
Color Image ◽  
Image Intensifier ◽  
Thickness Measurement ◽  
Imaging Plate ◽  
Technical Guide ◽  
Plant Components

Technical Guide for Diagnostics of Power Plant Components Technique due to Thickness Measurement by Digital Radiography, JEAG 4224–2009, was issued from Nuclear Standard Committee of Japan Electric Association on June 2009. Two types of digital radiography are applied to thickness measurement; imaging plate (IP) and color image intensifier (Color I. I. ). Organization and detailed contents of the technical guide is introduced in this paper.

Diagnosis of hermetic zone of containment envelope of nuclear power plant on basis of control of geometry and mechanical properties of containment

2020 ◽  
pp. 195-199
Author(s):  
V.V. Potapov ◽  
V.A. Il’in
Keyword(s):  
Mechanical Properties ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Laser Scanning ◽  
Nuclear Power Plants ◽  
Thickness Measurement ◽  
The State

The features for application of laser scanning of the lining geometry, the thickness measurement of the lining and the measurement of hardness with the subsequent assessment of mechanical properties to monitor the state of the pressurized volume of the containment envelope of nuclear power plants with VVER are considered.

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