ANALYSIS OF ROUND ROBIN TEST FOR ULTRASONIC THICKNESS MEASUREMENT OF WALL THINNED PIPE IN NUCLEAR POWER PLANT

2008 ◽  
Author(s):  
Dae-Hoon Lee ◽  
Seung-Joon Lee ◽  
Joon-Hyun Lee ◽  
Sung-Ho Lee ◽  
Donald O. Thompson ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Thickness Measurement ◽  
Round Robin ◽  
Round Robin Test ◽  
Ultrasonic Thickness Measurement ◽  
Ultrasonic Thickness

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.

Comparison between Conventional and Performance Demonstration UT Method by Round Robin Test

2006 ◽  
Vol 321-323 ◽  
pp. 1754-1757
Author(s):  
Yong Sik Kim ◽  
Seung Han Yang ◽  
Byung Sik Yoon ◽  
Hee Jong Lee
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Ultrasonic Testing ◽  
Nuclear Power ◽  
Round Robin ◽  
Round Robin Test ◽  
Examination Result ◽  
And Performance ◽  
Main Components ◽  
Performance Demonstration

The results of ultrasonic testing performed during in-service inspection period for main components of nuclear power plant are affected by the performance of each inspector. To enhance the inspection reliability, the more restrictive qualification is required. KEPRI established Korean performance demonstration (KPD) system for the ultrasonic testing personnel, equipment and procedure which applied to the piping examination of nuclear power plant. A round robin test was conducted to evaluate the reliability of examination result by comparing conventional (DAC) UT and performance demonstration (PD) UT method. Participants took detection/length sizing test and depth sizing test using DAC method and PD method. The results showed that the PD method was preciser and more accurate than the conventional DAC method in length and depth sizing regardless of field experience and PD qualification status.

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.

DEGRADATION ASSESSMENT OF NUCLEAR POWER PLANT EXTRACTION STEAM PIPING AFTER LONG TERM SERVICE

2016 ◽  
Vol 78 (9) ◽  
Author(s):  
M. A. Khattak ◽  
A. Mukhtar ◽  
Imran S. S. Ghumman ◽  
Saeed Badshah ◽  
Rafiullah Khan ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Thickness Measurement ◽  
Radiographic Examination ◽  
Pipe Material ◽  
Metallographic Examination ◽  
Plant Extraction ◽  
Ultrasonic Thickness Measurement ◽  
Corrosion Pits ◽  
Ultrasonic Thickness

Degradation due to ageing in a Nuclear Power Plant’s Extraction Steam Piping has been assessed. Samples of twelve years old seamless carbon steel SA 106B pipe have been taken and subjected to metallographic examination, hardness testing, radiographic examination and ultrasonic thickness measurement to investigate and analyze ageing in piping material. Metallographic examination of aged sample revealed irregularly distributed graphite nodules in ferrite grains and on grain boundaries as well, the reduction in pearlite phase has also been observed from 40% to 25%. This Transformation in microstructure has reduced hardness of steel. Reduction in hardness has found 20.4% and 0.7% on inner and outer layer of the pipe material respectively. Corrosion pits having average depth of 0.07 mm have been found on external surface. Radiograph of aged pipe revealed material removal and wall thinning due to erosion on inner surface of pipe. The extent of erosion had been checked, which has found 8.7%.

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