Overview of the preliminary design of the ITER plasma control system

J.A. Snipes, R. Albanese, G. Ambrosino, R. Ambrosino, V. Amoskov, T.C. Blanken, S. Bremond, M. Cinque, G. De Tommasi, P.C. De Vries, N. Eidietis, F. Felici, R. Felton, J. Ferron, A. Formisano, Y. Gribov, M. Hosokawa, A. Hyatt, D. Humphreys, G. JacksonA. Kavin, R. Khayrutdinov, D. Kim, S.H. Kim, S. Konovalov, E. Lamzin, M. Lehnen, V. Lukash, P. Lomas, M. Mattei, A. Mineev, P. Moreau, G. Neu, R. Nouailletas, G. Pautasso, A. Pironti, C. Rapson, G. Raupp, T. Ravensbergen, F. Rimini, M. Schneider, J.M. Travere, W. Treutterer, F. Villone, M. Walker, A. Welander, A. Winter, L. Zabeo

Research output: Contribution to journalArticleAcademicpeer-review

12 Citations (Scopus)

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.

Original languageEnglish
Article number125001
Number of pages10
JournalNuclear Fusion
Volume57
Issue number12
DOIs
Publication statusPublished - 11 Sep 2017

Fingerprint

plasma control
magnetic control
heating
plasma currents
pellets
systems engineering
simulators
topology
helium
injection
requirements
kinetics

Keywords

  • disruptions
  • ITER
  • plasma control

Cite this

Snipes, J. A., Albanese, R., Ambrosino, G., Ambrosino, R., Amoskov, V., Blanken, T. C., ... Zabeo, L. (2017). Overview of the preliminary design of the ITER plasma control system. Nuclear Fusion, 57(12), [125001]. https://doi.org/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. In: Nuclear Fusion. 2017 ; Vol. 57, No. 12.
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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.",
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Snipes, JA, Albanese, R, Ambrosino, G, Ambrosino, R, Amoskov, V, Blanken, TC, Bremond, S, Cinque, M, De Tommasi, G, De Vries, PC, 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, SH, 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, JM, Treutterer, W, Villone, F, Walker, M, Welander, A, Winter, A & Zabeo, L 2017, 'Overview of the preliminary design of the ITER plasma control system', Nuclear Fusion, vol. 57, no. 12, 125001. https://doi.org/10.1088/1741-4326/aa8177

Overview of the preliminary design of the ITER plasma control system. / 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.

In: Nuclear Fusion, Vol. 57, No. 12, 125001, 11.09.2017.

Research output: Contribution to journalArticleAcademicpeer-review

TY - JOUR

T1 - Overview of the preliminary design of the ITER plasma control system

AU - Snipes, J.A.

AU - Albanese, R.

AU - Ambrosino, G.

AU - Ambrosino, R.

AU - Amoskov, V.

AU - Blanken, T.C.

AU - Bremond, S.

AU - Cinque, M.

AU - De Tommasi, G.

AU - De Vries, P.C.

AU - Eidietis, N.

AU - Felici, F.

AU - Felton, R.

AU - Ferron, J.

AU - Formisano, A.

AU - Gribov, Y.

AU - Hosokawa, M.

AU - Hyatt, A.

AU - Humphreys, D.

AU - Jackson, G.

AU - Kavin, A.

AU - Khayrutdinov, R.

AU - Kim, D.

AU - Kim, S.H.

AU - Konovalov, S.

AU - Lamzin, E.

AU - Lehnen, M.

AU - Lukash, V.

AU - Lomas, P.

AU - Mattei, M.

AU - Mineev, A.

AU - Moreau, P.

AU - Neu, G.

AU - Nouailletas, R.

AU - Pautasso, G.

AU - Pironti, A.

AU - Rapson, C.

AU - Raupp, G.

AU - Ravensbergen, T.

AU - Rimini, F.

AU - Schneider, M.

AU - Travere, J.M.

AU - Treutterer, W.

AU - Villone, F.

AU - Walker, M.

AU - Welander, A.

AU - Winter, A.

AU - Zabeo, L.

PY - 2017/9/11

Y1 - 2017/9/11

N2 - 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.

AB - 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.

KW - disruptions

KW - ITER

KW - plasma control

UR - http://www.scopus.com/inward/record.url?scp=85034429160&partnerID=8YFLogxK

U2 - 10.1088/1741-4326/aa8177

DO - 10.1088/1741-4326/aa8177

M3 - Article

AN - SCOPUS:85034429160

VL - 57

JO - Nuclear Fusion

JF - Nuclear Fusion

SN - 0029-5515

IS - 12

M1 - 125001

ER -

Snipes JA, Albanese R, Ambrosino G, Ambrosino R, Amoskov V, Blanken TC et al. Overview of the preliminary design of the ITER plasma control system. Nuclear Fusion. 2017 Sep 11;57(12). 125001. https://doi.org/10.1088/1741-4326/aa8177