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Diagnostics for plasma control : from ITER to DEMO

(2019) FUSION ENGINEERING AND DESIGN. 146(A). p.465-472
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Abstract
The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical and physics limits, while its front-end components will be subject to strong adverse effects within the nuclear and high temperature plasma environment. The ongoing developments for the ITER D&C system represent an important starting point for progressing towards DEMO. Requirements for detailed exploration of physics are however pushing the ITER diagnostic design towards using sophisticated methods and aiming for large spatial coverage and high signal intensities, so that many front-end components have to be mounted in forward positions. In many cases this results in a rapid aging of diagnostic components, so that additional measures like protection shutters, plasma based mirror cleaning or modular approaches for frequent maintenance and exchange are being developed. Under the even stronger fluences of plasma particles, neutron/gamma and radiation loads on DEMO, durable and reliable signals for plasma control can only be obtained by selecting diagnostic methods with regard to their robustness, and retracting vulnerable front-end components into protected locations. Based on this approach, an initial DEMO D&C concept is presented, which covers all major control issues by signals to be derived from at least two different diagnostic methods (risk mitigation).
Keywords
Mechanical Engineering, General Materials Science, Nuclear Energy and Engineering, Civil and Structural Engineering, ITER, DEMO, Tokamak, Plasma control, Plasma diagnostics, RESEARCH-AND-DEVELOPMENT, HALL SENSORS, DENSITY-MEASUREMENTS, DESIGN, ISSUES, INTEGRATION, ELECTRON, SYSTEM, EDGE

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MLA
Biel, Wolfgang, et al. “Diagnostics for Plasma Control : From ITER to DEMO.” FUSION ENGINEERING AND DESIGN, vol. 146, no. A, 2019, pp. 465–72, doi:10.1016/j.fusengdes.2018.12.092.
APA
Biel, W., Albanese, R., Ambrosino, R., Ariola, M., Berkel, M. V., Bolshakova, I., … Zohm, H. (2019). Diagnostics for plasma control : from ITER to DEMO. FUSION ENGINEERING AND DESIGN, 146(A), 465–472. https://doi.org/10.1016/j.fusengdes.2018.12.092
Chicago author-date
Biel, Wolfgang, R. Albanese, R. Ambrosino, M. Ariola, M.V. Berkel, I. Bolshakova, K.J. Brunner, et al. 2019. “Diagnostics for Plasma Control : From ITER to DEMO.” FUSION ENGINEERING AND DESIGN 146 (A): 465–72. https://doi.org/10.1016/j.fusengdes.2018.12.092.
Chicago author-date (all authors)
Biel, Wolfgang, R. Albanese, R. Ambrosino, M. Ariola, M.V. Berkel, I. Bolshakova, K.J. Brunner, R. Cavazzana, M. Cecconello, S. Conroy, A. Dinklage, I. Duran, R. Dux, T. Eade, S. Entler, G. Ericsson, E. Fable, D. Farina, L. Figini, C. Finotti, Th. Franke, L. Giacomelli, L. Giannone, W. Gonzalez, A. Hjalmarsson, M. Hron, F. Janky, A. Kallenbach, J. Kogoj, R. König, O. Kudlacek, R. Luis, A. Malaquias, O. Marchuk, G. Marchiori, M. Mattei, F. Maviglia, G. De Masi, D. Mazon, H. Meister, K. Meyer, D. Micheletti, S. Nowak, Ch. Piron, A. Pironti, N. Rispoli, V. Rohde, G. Sergienko, S. El Shawish, M. Siccinio, A. Silva, F. da Silva, C. Sozzi, M. Tardocchi, M. Tokar, W. Treutterer, and H. Zohm. 2019. “Diagnostics for Plasma Control : From ITER to DEMO.” FUSION ENGINEERING AND DESIGN 146 (A): 465–472. doi:10.1016/j.fusengdes.2018.12.092.
Vancouver
1.
Biel W, Albanese R, Ambrosino R, Ariola M, Berkel MV, Bolshakova I, et al. Diagnostics for plasma control : from ITER to DEMO. FUSION ENGINEERING AND DESIGN. 2019;146(A):465–72.
IEEE
[1]
W. Biel et al., “Diagnostics for plasma control : from ITER to DEMO,” FUSION ENGINEERING AND DESIGN, vol. 146, no. A, pp. 465–472, 2019.
@article{8666977,
  abstract     = {The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical and physics limits, while its front-end components will be subject to strong adverse effects within the nuclear and high temperature plasma environment. The ongoing developments for the ITER D&C system represent an important starting point for progressing towards DEMO. Requirements for detailed exploration of physics are however pushing the ITER diagnostic design towards using sophisticated methods and aiming for large spatial coverage and high signal intensities, so that many front-end components have to be mounted in forward positions. In many cases this results in a rapid aging of diagnostic components, so that additional measures like protection shutters, plasma based mirror cleaning or modular approaches for frequent maintenance and exchange are being developed.

Under the even stronger fluences of plasma particles, neutron/gamma and radiation loads on DEMO, durable and reliable signals for plasma control can only be obtained by selecting diagnostic methods with regard to their robustness, and retracting vulnerable front-end components into protected locations. Based on this approach, an initial DEMO D&C concept is presented, which covers all major control issues by signals to be derived from at least two different diagnostic methods (risk mitigation).},
  author       = {Biel, Wolfgang and Albanese, R. and Ambrosino, R. and Ariola, M. and Berkel, M.V. and Bolshakova, I. and Brunner, K.J. and Cavazzana, R. and Cecconello, M. and Conroy, S. and Dinklage, A. and Duran, I. and Dux, R. and Eade, T. and Entler, S. and Ericsson, G. and Fable, E. and Farina, D. and Figini, L. and Finotti, C. and Franke, Th. and Giacomelli, L. and Giannone, L. and Gonzalez, W. and Hjalmarsson, A. and Hron, M. and Janky, F. and Kallenbach, A. and Kogoj, J. and König, R. and Kudlacek, O. and Luis, R. and Malaquias, A. and Marchuk, O. and Marchiori, G. and Mattei, M. and Maviglia, F. and De Masi, G. and Mazon, D. and Meister, H. and Meyer, K. and Micheletti, D. and Nowak, S. and Piron, Ch. and Pironti, A. and Rispoli, N. and Rohde, V. and Sergienko, G. and El Shawish, S. and Siccinio, M. and Silva, A. and da Silva, F. and Sozzi, C. and Tardocchi, M. and Tokar, M. and Treutterer, W. and Zohm, H.},
  issn         = {0920-3796},
  journal      = {FUSION ENGINEERING AND DESIGN},
  keywords     = {Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering,ITER,DEMO,Tokamak,Plasma control,Plasma diagnostics,RESEARCH-AND-DEVELOPMENT,HALL SENSORS,DENSITY-MEASUREMENTS,DESIGN,ISSUES,INTEGRATION,ELECTRON,SYSTEM,EDGE},
  language     = {eng},
  location     = {Messina, Italy},
  number       = {A},
  pages        = {465--472},
  title        = {Diagnostics for plasma control : from ITER to DEMO},
  url          = {http://dx.doi.org/10.1016/j.fusengdes.2018.12.092},
  volume       = {146},
  year         = {2019},
}

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