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Title: Overview of the preliminary design of the ITER plasma control system

Abstract

An overview of the Preliminary Design of the ITER Plasma Control System (PCS) is described here, which focusses on the needs for 1st plasma and early plasma operation in hydrogen/helium (H/He) up to a plasma current of 15 MA with moderate auxiliary heating power in low confinement mode (L-mode). Candidate control schemes for basic magnetic control, including divertor operation and kinetic control of the electron density with gas puffing and pellet injection, were developed. Commissioning of the auxiliary heating systems is included as well as support functions for stray field topology and real-time plasma boundary reconstruction. Initial exception handling schemes for faults of essential plant systems and for disruption protection were developed. The PCS architecture was also developed to be capable of handling basic control for early commissioning and the advanced control functions that will be needed for future high performance operation. A plasma control simulator is also being developed to test and validate control schemes. To handle the complexity of the ITER PCS, a systems engineering approach has been adopted with the development of a plasma control database to keep track of all control requirements.

Authors:
 [1];  [2];  [2];  [2];  [3]; ORCiD logo [4];  [5];  [2]; ORCiD logo [2];  [1];  [6];  [4];  [7];  [6];  [2];  [1];  [1];  [6];  [6];  [6] more »;  [3];  [8];  [9];  [1];  [8];  [3];  [1];  [8];  [7];  [2];  [3];  [5];  [10];  [5];  [10];  [2]; ORCiD logo [10];  [10];  [4];  [7];  [1];  [5];  [10];  [2];  [6];  [6];  [1];  [1] « less
  1. ITER Organization, St. Paul Lez Durance (France)
  2. Consorzio CREATE, Napoli (Italy)
  3. D. V. Efremov Inst. of Electrophysical Apparatus, St. Petersburg (Russian Federation)
  4. Eindhoven Univ. of Technology (Netherlands)
  5. CEA, IRFM, St. Paul Lez Durance (France)
  6. Central Atomics, San Diego, CA (United States)
  7. Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE), EURATOM/UKAEA Fusion Association
  8. National Research Centre (NRC), Moscow (Russian Federation). Kurchatov Inst. (NRCKI)
  9. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  10. Max Planck Inst. fur Plasmaphysik, Garching (Germany)
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1434642
Grant/Contract Number:  
AC02-09-CH11466
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 57; Journal Issue: 12; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats

Snipes, J. A., Albanese, R., Ambrosino, G., Ambrosino, R., Amoskov, V., Blanken, T. C., Bremond, S., Cinque, M., de Tommasi, G., de Vries, P. C., Eidietis, N., Felici, F., Felton, R., Ferron, J., Formisano, A., Gribov, Y., Hosokawa, M., Hyatt, A., Humphreys, D., Jackson, G., Kavin, A., Khayrutdinov, R., Kim, D., Kim, S. H., Konovalov, S., Lamzin, E., Lehnen, M., Lukash, V., Lomas, P., Mattei, M., Mineev, A., Moreau, P., Neu, G., Nouailletas, R., Pautasso, G., Pironti, A., Rapson, C., Raupp, G., Ravensbergen, T., Rimini, F., Schneider, M., Travere, J. -M., Treutterer, W., Villone, F., Walker, M., Welander, A., Winter, A., and Zabeo, L. Overview of the preliminary design of the ITER plasma control system. United States: N. p., 2017. Web. doi:10.1088/1741-4326/aa8177.
Snipes, J. A., Albanese, R., Ambrosino, G., Ambrosino, R., Amoskov, V., Blanken, T. C., Bremond, S., Cinque, M., de Tommasi, G., de Vries, P. C., Eidietis, N., Felici, F., Felton, R., Ferron, J., Formisano, A., Gribov, Y., Hosokawa, M., Hyatt, A., Humphreys, D., Jackson, G., Kavin, A., Khayrutdinov, R., Kim, D., Kim, S. H., Konovalov, S., Lamzin, E., Lehnen, M., Lukash, V., Lomas, P., Mattei, M., Mineev, A., Moreau, P., Neu, G., Nouailletas, R., Pautasso, G., Pironti, A., Rapson, C., Raupp, G., Ravensbergen, T., Rimini, F., Schneider, M., Travere, J. -M., Treutterer, W., Villone, F., Walker, M., Welander, A., Winter, A., & Zabeo, L. Overview of the preliminary design of the ITER plasma control system. United States. doi:10.1088/1741-4326/aa8177.
Snipes, J. A., Albanese, R., Ambrosino, G., Ambrosino, R., Amoskov, V., Blanken, T. C., Bremond, S., Cinque, M., de Tommasi, G., de Vries, P. C., Eidietis, N., Felici, F., Felton, R., Ferron, J., Formisano, A., Gribov, Y., Hosokawa, M., Hyatt, A., Humphreys, D., Jackson, G., Kavin, A., Khayrutdinov, R., Kim, D., Kim, S. H., Konovalov, S., Lamzin, E., Lehnen, M., Lukash, V., Lomas, P., Mattei, M., Mineev, A., Moreau, P., Neu, G., Nouailletas, R., Pautasso, G., Pironti, A., Rapson, C., Raupp, G., Ravensbergen, T., Rimini, F., Schneider, M., Travere, J. -M., Treutterer, W., Villone, F., Walker, M., Welander, A., Winter, A., and Zabeo, L. Mon . "Overview of the preliminary design of the ITER plasma control system". United States. doi:10.1088/1741-4326/aa8177. https://www.osti.gov/servlets/purl/1434642.
@article{osti_1434642,
title = {Overview of the preliminary design of the ITER plasma control system},
author = {Snipes, J. A. and Albanese, R. and Ambrosino, G. and Ambrosino, R. and Amoskov, V. and Blanken, T. C. and Bremond, S. and Cinque, M. and de Tommasi, G. and de Vries, P. C. and Eidietis, N. and Felici, F. and Felton, R. and Ferron, J. and Formisano, A. and Gribov, Y. and Hosokawa, M. and Hyatt, A. and Humphreys, D. and Jackson, G. and Kavin, A. and Khayrutdinov, R. and Kim, D. and Kim, S. H. and Konovalov, S. and Lamzin, E. and Lehnen, M. and Lukash, V. and Lomas, P. and Mattei, M. and Mineev, A. and Moreau, P. and Neu, G. and Nouailletas, R. and Pautasso, G. and Pironti, A. and Rapson, C. and Raupp, G. and Ravensbergen, T. and Rimini, F. and Schneider, M. and Travere, J. -M. and Treutterer, W. and Villone, F. and Walker, M. and Welander, A. and Winter, A. and Zabeo, L.},
abstractNote = {An overview of the Preliminary Design of the ITER Plasma Control System (PCS) is described here, which focusses on the needs for 1st plasma and early plasma operation in hydrogen/helium (H/He) up to a plasma current of 15 MA with moderate auxiliary heating power in low confinement mode (L-mode). Candidate control schemes for basic magnetic control, including divertor operation and kinetic control of the electron density with gas puffing and pellet injection, were developed. Commissioning of the auxiliary heating systems is included as well as support functions for stray field topology and real-time plasma boundary reconstruction. Initial exception handling schemes for faults of essential plant systems and for disruption protection were developed. The PCS architecture was also developed to be capable of handling basic control for early commissioning and the advanced control functions that will be needed for future high performance operation. A plasma control simulator is also being developed to test and validate control schemes. To handle the complexity of the ITER PCS, a systems engineering approach has been adopted with the development of a plasma control database to keep track of all control requirements.},
doi = {10.1088/1741-4326/aa8177},
journal = {Nuclear Fusion},
number = 12,
volume = 57,
place = {United States},
year = {2017},
month = {9}
}

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