Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak

Md Mahbub Alam; Md Dulal Hossain; Md Shafiul Alam Chowdhury

doi:doi:10.11648/j.ijem.20190301.13

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Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak

Md Mahbub Alam, Md Dulal Hossain, Md Shafiul Alam Chowdhury

Published in International Journal of Engineering Management (Volume 3, Issue 1)

Received: 6 June 2019 Accepted: 10 July 2019 Published: 24 July 2019

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Abstract

A novel, efficient and precise real-time display system to monitor the plasma shape and position during the discharge of the tokamak has been offered in this study for the observation of the continuous behavior of the plasma that is produced inside the vacuum vessel. The observed behavior of the plasma can provide indications for the control and operation of the tokamak to achieve long time discharge. The display system can display the plasma cross-sectional view of the last closed flux surface (LCFS) with the position of the vacuum vessel wall and the X-points position with the setting of the divertor plates at a big screen in real-time. The display system offers not only the visual image of the plasma but also time evolution graphs of various plasma parameters such as the plasma current (I_P), poloidal field coils currents (I_PF), emission of H_α, transport of the oxygen impurity, major radius (R), minor radius (a), plasma elongation (κ) and triangularity (δ) in real-time. For the remote participation to the experiments, the display system has a subsystem that can record the entire display frame and the time evolution graphs of the various plasma parameters as video files. The recorded video files are accessible through online by the remote participants during the operation of the tokamak. In addition, the display system has an emergency safety notification system that can identify the critical condition of the tokamak during its operation and can notify the occurrences of any critical or abnormal situations by generating an alarm. The overall display system and its subsystems have been designed and integrated with the real-time hardware equipment of the National Instruments Corporation (NI) and the entire data acquisition and computational systems have been developed by the LabVIEW programming Language.

Published in	International Journal of Engineering Management (Volume 3, Issue 1)
DOI	10.11648/j.ijem.20190301.13
Page(s)	12-16
Creative Commons	This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.
Copyright	Copyright © The Author(s), 2019. Published by Science Publishing Group

Keywords

Display System, Long Time Discharge, Plasma Shape, Position, Real-time, Tokamak, Safety Notification System

References

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[3]	https://www.iter.org/newsline/128/247
[4]	Zhang, X., Hu, et al., “The development of data acquisition and remote real-time display system for EAST NBI,” Journal of Fusion Energy, Vol. 32 (5), pp. 566-569, 2013.
[5]	Shu, Shuangbao, et al., “Plasma image edge detection based on the visible camera in the EAST device,” SpringerPlus, vol. 5 (1), p. 2050, 2016.
[6]	Ellis, J., et al., "A real time plasma boundary determination and display system using transputers," Proceedings of the 18th Symposium on Fusion Technology, pp. 743-746. 1994.
[7]	Puig Sitjes, A., et al., “Wendelstein 7-x near real-time image diagnostic system for plasma-facing components protection,” Fusion Science and Technology, vol. 74.1-2, pp. 116-124, 2018.
[8]	Hasegawa, Makoto, et al., “Modification of plasma control system and hot-wall temperature control system for long-duration plasma sustainment in QUEST,” Fusion Engineering and Design, vol. 129, pp. 202-206, 2018.
[9]	Hartfuss, H. J., R. König, and A. Werner, “Diagnostics for steady state plasmas,” Plasma physics and controlled fusion, vol. 48 (10), p. R83, 2006.
[10]	Rodríguez, Alfonso, et al., “Fpga-based high-performance embedded systems for adaptive edge computing in cyber-physical systems: The artico3 framework,” Sensors, vol. 18 (6), p. 1877, 8 June 2018.
[11]	Lidozzi, Alessandro, et al., “Towards LabVIEW and system on module for power electronics and drives control applications,” Proceedings of the IECON 2016-42nd Annual Conference of the IEEE Industrial Electronics Society. IEEE, 2016.
[12]	Hasegawa, M., et al., “Development of plasma control system for divertor configuration on QUEST,” Fusion Engineering and Design, vol. 88 (6-8), pp. 1074-1077, 2013.
[13]	Kurihara, K., “A new shape reproduction method based on the Cauchy-condition surface for real-time tokamak reactor control,” Fusion engineering and design, vol. 51, pp. 1049 (8), 2000.
[14]	Nakamura, Kazuo, et al. "Characteristics of SVD in ST Plasma Shape Reproduction Method Based on CCS," Plasma Fusion Res., vol. 8, P. 1048, 2009.
[15]	K. Nakamura et al., “Shape reconstruction of RF-driven divertor plasma on QUEST,” IEEE Trans. Plasma Sci. vol. 42 (9), p. 2309, 2014.

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APA Style

Md Mahbub Alam, Md Dulal Hossain, Md Shafiul Alam Chowdhury. (2019). Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak. International Journal of Engineering Management, 3(1), 12-16. https://doi.org/10.11648/j.ijem.20190301.13

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ACS Style

Md Mahbub Alam; Md Dulal Hossain; Md Shafiul Alam Chowdhury. Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak. Int. J. Eng. Manag. 2019, 3(1), 12-16. doi: 10.11648/j.ijem.20190301.13

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AMA Style

Md Mahbub Alam, Md Dulal Hossain, Md Shafiul Alam Chowdhury. Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak. Int J Eng Manag. 2019;3(1):12-16. doi: 10.11648/j.ijem.20190301.13

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@article{10.11648/j.ijem.20190301.13,
  author = {Md Mahbub Alam and Md Dulal Hossain and Md Shafiul Alam Chowdhury},
  title = {Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak},
  journal = {International Journal of Engineering Management},
  volume = {3},
  number = {1},
  pages = {12-16},
  doi = {10.11648/j.ijem.20190301.13},
  url = {https://doi.org/10.11648/j.ijem.20190301.13},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijem.20190301.13},
  abstract = {A novel, efficient and precise real-time display system to monitor the plasma shape and position during the discharge of the tokamak has been offered in this study for the observation of the continuous behavior of the plasma that is produced inside the vacuum vessel. The observed behavior of the plasma can provide indications for the control and operation of the tokamak to achieve long time discharge. The display system can display the plasma cross-sectional view of the last closed flux surface (LCFS) with the position of the vacuum vessel wall and the X-points position with the setting of the divertor plates at a big screen in real-time. The display system offers not only the visual image of the plasma but also time evolution graphs of various plasma parameters such as the plasma current (IP), poloidal field coils currents (IPF), emission of Hα, transport of the oxygen impurity, major radius (R), minor radius (a), plasma elongation (κ) and triangularity (δ) in real-time. For the remote participation to the experiments, the display system has a subsystem that can record the entire display frame and the time evolution graphs of the various plasma parameters as video files. The recorded video files are accessible through online by the remote participants during the operation of the tokamak. In addition, the display system has an emergency safety notification system that can identify the critical condition of the tokamak during its operation and can notify the occurrences of any critical or abnormal situations by generating an alarm. The overall display system and its subsystems have been designed and integrated with the real-time hardware equipment of the National Instruments Corporation (NI) and the entire data acquisition and computational systems have been developed by the LabVIEW programming Language.},
 year = {2019}
}

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TY  - JOUR
T1  - Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak
AU  - Md Mahbub Alam
AU  - Md Dulal Hossain
AU  - Md Shafiul Alam Chowdhury
Y1  - 2019/07/24
PY  - 2019
N1  - https://doi.org/10.11648/j.ijem.20190301.13
DO  - 10.11648/j.ijem.20190301.13
T2  - International Journal of Engineering Management
JF  - International Journal of Engineering Management
JO  - International Journal of Engineering Management
SP  - 12
EP  - 16
PB  - Science Publishing Group
SN  - 2640-1568
UR  - https://doi.org/10.11648/j.ijem.20190301.13
AB  - A novel, efficient and precise real-time display system to monitor the plasma shape and position during the discharge of the tokamak has been offered in this study for the observation of the continuous behavior of the plasma that is produced inside the vacuum vessel. The observed behavior of the plasma can provide indications for the control and operation of the tokamak to achieve long time discharge. The display system can display the plasma cross-sectional view of the last closed flux surface (LCFS) with the position of the vacuum vessel wall and the X-points position with the setting of the divertor plates at a big screen in real-time. The display system offers not only the visual image of the plasma but also time evolution graphs of various plasma parameters such as the plasma current (IP), poloidal field coils currents (IPF), emission of Hα, transport of the oxygen impurity, major radius (R), minor radius (a), plasma elongation (κ) and triangularity (δ) in real-time. For the remote participation to the experiments, the display system has a subsystem that can record the entire display frame and the time evolution graphs of the various plasma parameters as video files. The recorded video files are accessible through online by the remote participants during the operation of the tokamak. In addition, the display system has an emergency safety notification system that can identify the critical condition of the tokamak during its operation and can notify the occurrences of any critical or abnormal situations by generating an alarm. The overall display system and its subsystems have been designed and integrated with the real-time hardware equipment of the National Instruments Corporation (NI) and the entire data acquisition and computational systems have been developed by the LabVIEW programming Language.
VL  - 3
IS  - 1
ER  -

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Author Information

Md Mahbub Alam

Institute of Computer Science, Bangladesh Atomic Energy Commission, Agargaon, Dhaka, Bangladesh
Md Dulal Hossain

Institute of Computer Science, Bangladesh Atomic Energy Commission, Agargaon, Dhaka, Bangladesh
Md Shafiul Alam Chowdhury

Department of Computer Science and Engineering, Uttara University, Uttara, Dhaka, Bangladesh

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APA Style

Md Mahbub Alam, Md Dulal Hossain, Md Shafiul Alam Chowdhury. (2019). Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak. International Journal of Engineering Management, 3(1), 12-16. https://doi.org/10.11648/j.ijem.20190301.13

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ACS Style

Md Mahbub Alam; Md Dulal Hossain; Md Shafiul Alam Chowdhury. Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak. Int. J. Eng. Manag. 2019, 3(1), 12-16. doi: 10.11648/j.ijem.20190301.13

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AMA Style

Md Mahbub Alam, Md Dulal Hossain, Md Shafiul Alam Chowdhury. Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak. Int J Eng Manag. 2019;3(1):12-16. doi: 10.11648/j.ijem.20190301.13

Copy | Download

@article{10.11648/j.ijem.20190301.13,
  author = {Md Mahbub Alam and Md Dulal Hossain and Md Shafiul Alam Chowdhury},
  title = {Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak},
  journal = {International Journal of Engineering Management},
  volume = {3},
  number = {1},
  pages = {12-16},
  doi = {10.11648/j.ijem.20190301.13},
  url = {https://doi.org/10.11648/j.ijem.20190301.13},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijem.20190301.13},
  abstract = {A novel, efficient and precise real-time display system to monitor the plasma shape and position during the discharge of the tokamak has been offered in this study for the observation of the continuous behavior of the plasma that is produced inside the vacuum vessel. The observed behavior of the plasma can provide indications for the control and operation of the tokamak to achieve long time discharge. The display system can display the plasma cross-sectional view of the last closed flux surface (LCFS) with the position of the vacuum vessel wall and the X-points position with the setting of the divertor plates at a big screen in real-time. The display system offers not only the visual image of the plasma but also time evolution graphs of various plasma parameters such as the plasma current (IP), poloidal field coils currents (IPF), emission of Hα, transport of the oxygen impurity, major radius (R), minor radius (a), plasma elongation (κ) and triangularity (δ) in real-time. For the remote participation to the experiments, the display system has a subsystem that can record the entire display frame and the time evolution graphs of the various plasma parameters as video files. The recorded video files are accessible through online by the remote participants during the operation of the tokamak. In addition, the display system has an emergency safety notification system that can identify the critical condition of the tokamak during its operation and can notify the occurrences of any critical or abnormal situations by generating an alarm. The overall display system and its subsystems have been designed and integrated with the real-time hardware equipment of the National Instruments Corporation (NI) and the entire data acquisition and computational systems have been developed by the LabVIEW programming Language.},
 year = {2019}
}

Copy | Download

TY  - JOUR
T1  - Real-time Display System to Monitor Plasma Shape and Position During the Discharge of the Tokamak
AU  - Md Mahbub Alam
AU  - Md Dulal Hossain
AU  - Md Shafiul Alam Chowdhury
Y1  - 2019/07/24
PY  - 2019
N1  - https://doi.org/10.11648/j.ijem.20190301.13
DO  - 10.11648/j.ijem.20190301.13
T2  - International Journal of Engineering Management
JF  - International Journal of Engineering Management
JO  - International Journal of Engineering Management
SP  - 12
EP  - 16
PB  - Science Publishing Group
SN  - 2640-1568
UR  - https://doi.org/10.11648/j.ijem.20190301.13
AB  - A novel, efficient and precise real-time display system to monitor the plasma shape and position during the discharge of the tokamak has been offered in this study for the observation of the continuous behavior of the plasma that is produced inside the vacuum vessel. The observed behavior of the plasma can provide indications for the control and operation of the tokamak to achieve long time discharge. The display system can display the plasma cross-sectional view of the last closed flux surface (LCFS) with the position of the vacuum vessel wall and the X-points position with the setting of the divertor plates at a big screen in real-time. The display system offers not only the visual image of the plasma but also time evolution graphs of various plasma parameters such as the plasma current (IP), poloidal field coils currents (IPF), emission of Hα, transport of the oxygen impurity, major radius (R), minor radius (a), plasma elongation (κ) and triangularity (δ) in real-time. For the remote participation to the experiments, the display system has a subsystem that can record the entire display frame and the time evolution graphs of the various plasma parameters as video files. The recorded video files are accessible through online by the remote participants during the operation of the tokamak. In addition, the display system has an emergency safety notification system that can identify the critical condition of the tokamak during its operation and can notify the occurrences of any critical or abnormal situations by generating an alarm. The overall display system and its subsystems have been designed and integrated with the real-time hardware equipment of the National Instruments Corporation (NI) and the entire data acquisition and computational systems have been developed by the LabVIEW programming Language.
VL  - 3
IS  - 1
ER  -

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