Qualification of phased array ultrasonic examination on T-joint weld of austenitic stainless steel for ITER vacuum vessel

Park, Chulkyu; Jin, Shijiu; Kim, H.S.; Hong, K.H.; Lee, Y.J.; Ahn, H.J.; Chung, Woosuk; Jung, Yo Han; Roh, Beom-Seok; Sa, J.W.; Choi, Chang Ho

doi:10.1016/j.fusengdes.2016.01.015

Cited by 13 publications

(10 citation statements)

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“…These developments will need to include both technologies specific to fusion reactors, such as monitoring of power output via neutron yields [53] and of surface morphology of plasma-facing components [54], e.g. breeder blankets, but also more conventional structural health monitoring during operations and non-destructive evaluation during manufacture and maintenance, for instance ultrasound examination of welds [55] and hydrostatic heat sinks [56,57].…”

Section: Discussionmentioning

confidence: 99%

An integrated digital framework for the design, build and operation of fusion power plants

et al. 2019

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The development of a commercial fusion power plant presents a unique set of challenges associated with the complexity of the systems, the integration of novel technologies, the likely diversity and distribution of the organizations involved, and the scale of resources required. These challenges are reviewed and compared to those for other complex engineering systems. A framework for creating a digital environment that integrates research, test, design and operational data is discussed and is based on combining the integrated nuclear digital environment (INDE), proposed recently for nuclear fission power plants, with the hierarchical pyramid of test and simulation used in the aerospace industry. The framework offers the opportunity to plan modelling strategies that allow large design domains to be explored prior to optimizing a detailed design for construction; and in this context, the relationship between measurements and predictions are explored. The use of the framework to guide the socio-technical activity associated with a distributed and collaborative design process is discussed together with its potential benefits and the technology gaps that need to be addressed in order to realize them. These benefits include shorter development times, reduced costs and improvements in credibility, operability, reliability and safety.

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Section: Discussionmentioning

confidence: 99%

An integrated digital framework for the design, build and operation of fusion power plants

et al. 2019

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“…The lower part of Figure shows various manufacturing progresses and products, which are a huge outward appearance of the VV (40° sector), and it can be easily supposed that this procurement needs many welding points to manufacture every part of the entity for assembling a whole VV. To overcome this difficult challenge, the phased array ultrasonic examination (PAUT), which is applied to the double‐sided T‐shaped austenitic welds of the ITER VV as a major nondestructive examination method, has been developed in Korea …”

Section: Progress Of the Iter Projectmentioning

confidence: 99%

“…To overcome this difficult challenge, the phased array ultrasonic examination (PAUT), which is applied to the double-sided T-shaped austenitic welds of the ITER VV as a major nondestructive examination method, has been developed in Korea. 12 Figure 13 shows the VV ports, which provide access to the plasma chamber for the maintenance and replacement of invessel component and support the plasma-facing parts of diagnostic, test blanket modules and plasma heating systems. Port packages of KODA procurement consist of a total of 35 sets of equatorial and lower ports, 3 sets of neutral beam port in-wall shield, 9 sets of VV gravity support, and 3 sets of neutral beam duct liner and sealing flanges.…”

Section: Two Vv Sectorsmentioning

confidence: 99%

Fusion energy development status in Korea

et al. 2017

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SummaryThis overview discusses the status of fusion energy development in the Republic of Korea. Korea studies fusion energy through research and development in 2 ways: one by performing the Korea Superconducting Tokamak Advanced Research (KSTAR) for a domestic approach and the other by participating in the international collaboration project ITER. Korea had remarkable progresses not only in KSTAR but also in the ITER project in 2016. In KSTAR, a world record of more than 70 seconds in high-performance plasma (H-mode) operation in the superconducting tokamak has been achieved. For the ITER project, toroidal field conductors have been successfully accomplished and the other major equipment such as vacuum vessel sectors, ports, and assembly tooling seem to be reaching an end. This paper deals with current research and development results on both fields of KSTAR study and ITER project progress.

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“…S-scan imaging is one of the most commonly used imaging modes due to its advantages of efficiency, flexibility, and wide inspection range. It is widely used in many fields, including aerospace [2], axles and bogie frames of rail vehicles [3,4], pressure vessels and pipelines [5,6], weld in ITER vacuum vessel and reactor pressure vessel of BWR [7,8] and steam turbine blade attachment area of nuclear power plant [9]. However, when using pulsed longitudinal wave mode detection, near-detection-surface defect echoes frequently overlap with interface echoes [10], making discernment of defect characteristics difficult.…”

Section: Introductionmentioning

confidence: 99%

Phased array ultrasonic S-scan testing of near-detection-surface defects based on a background subtraction algorithm

Tian

Wei

et al. 2022

Mater. Res. Express

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In phased array ultrasonic sector scanning testing, echoes from defects near the detection surface are often overlapped with interface echoes and cannot be characterized. Based on linear acoustic theory, a mathematical model combining the background subtraction and the sum of squares differences algorithm is established to extract the characteristics of near-detection-surface defect echoes. The upper surface of artificial notch defect is used as a near-detection-surface defect for detection. Specially, linear interpolation algorithm is used to suppress the effect of residual interface echo on the defect echo feature extraction and the effect of different interpolation factors is analyzed. The defect location and size were calculated based on the extracted defect characteristics. The simulation and experimental results indicate that the model can effectively extract the near-detection-surface defect echoes characteristics. Furthermore, when the interpolated signal reaches at least 500 MHz, residual interface echoes can be effectively suppressed. More importantly, according to the extracted defect echo characteristics, the localization and quantitative accuracies of near-surface defects can reach 0.2 mm and 0.3 mm, respectively. These findings provide an effective strategy for phased array ultrasonic sector scanning testing of near-surface defects.

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Qualification of phased array ultrasonic examination on T-joint weld of austenitic stainless steel for ITER vacuum vessel

Cited by 13 publications

References 1 publication

An integrated digital framework for the design, build and operation of fusion power plants

An integrated digital framework for the design, build and operation of fusion power plants

Fusion energy development status in Korea

Phased array ultrasonic S-scan testing of near-detection-surface defects based on a background subtraction algorithm

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