F. Koechl

Publications (10)0 Total impact

• Conference Proceeding: Optimisation of the ITER baseline scenario

  F Koechl, R Ambrosino, M Cavinato, G Corrigan, L Garzotti, C Labate, MATTEI M, D C McDonald, V Parail, G Saibene, R Sartori
  Proceedings 39th EPS Conference & 16th Int. Congress on Plasma Physics, 2012; 01/2012
• Conference Proceeding: Self-consistent predictive modelling of 15 MA inductive scenarios in ITER

  F Koechl, V Parail, MATTEI M, R Ambrosino, G Corrigan, L Garzotti, C Labate, D C McDonald
  Proceedings 38th conference on Plasma Physics; 01/2011
• Conference Proceeding: Integrated simulations of kick-triggered ELMs at JET

  F Koechl, G Corrigan, J Lönnroth, E Luna, MATTEI M, F Maviglia, D C McDonald, V Parail, G Saibene, JET EFDA contributors
  13th International Workshop on H-mode Physics and Transport Barriers, Oxford, UK; 01/2011
• Conference Proceeding: Development of ITER 15 MA ELMy H-mode Inductive Scenario

  C E KESSEL, D CAMPBELL, Y GRIBOV, G SAIBENE, G AMBROSINO, T CASPER, M CAVINATO, H FUJIEDA, R HAWRYLUK, L D HORTON, [......], MATTEI M, I NUNES, V PARAIL, A POLEVOI, A PORTONE, R SARTORI, A C C SIPS, P R THOMAS, A WELANDER, J WESLEY
  Proceedings 22nd IAEA Fusion Energy Conference (FEC 2008), Geneva (CH); 01/2008
• Article: ITER operational space for full plasma current H-mode operation

  M Mattei, M. Cavinato, G. Saibene, A. Portone, R. Albanese, G. Ambrosino, L. D. Horton, C. Kessel, F. Koechl, P. J. Lomas, I. Nunes, V. Parail, R. Sartori, A. C. C. Sips, P. R. Thomas
  Fusion Engineering and Design, v.84, 300-304 (2009).
• Source

  Available from: Bernard Pegourie

  Article: Integrated Modelling of Pellet Experiments at JET

  F. Koechl, G. Corrigan, D. Frigione, L. Garzotti, G. Kamelander, P Lang, H. Nehme, V. Parail, B. Pégourié, M. Valovič, S. Wiesen, JET EFDA Contributors
  McKenna, C.: 37th European Physical Society Conference on Plasma Physics. Contributed Papers, European Physical Society (2010).
• Source

  Available from: iaea.org

  Article: Integrated Simulation of ELM Triggered by Pellet through Energy Absorption and Transport Enhancement

  N Hayashi, V. Parail, F. Koechl, N. Aiba, T. Takizuka, S. Wiesen, P. T. Lang, N Oyama, T Ozeki
• Article: On the heating mix of ITER (invited paper)

  F Wagner, A. Becoulet, R. V. Budny, V. Erckmann, D. Farina, G. Giruzzi, Y. Kamada, A. Kaye, F. Koechl, K Lackner, [......], V. Parail, J M Park, G. Ramponi, O. Sauter, D Stork, P. R. Thomas, Q. M. Tran, D Ward, H. Zohm, C. Zucca
  Plasma Physics and Controlled Fusion, v.52 (2010).
• Article: ITER operational space for full plasma current H-mode operation

  M. Mattei, M. Cavinato, G. Saibene, A. Portone, R. Albanese, G. Ambrosino, L.D. Horton, C. Kessel, F. Koechl, P.J. Lomas, I. Nunes, V. Parail, R. Sartori, A.C.C. Sips, P.R. Thomas
  [show abstract] [hide abstract]
  ABSTRACT: Sensitivity studies performed as part of the ITER IO design review highlighted a very stiff dependence of the maximum Q attainable on the machine parameters. In particular, in the considered range, the achievable Q scales with Ip^4. As a consequence, the achievement of the ITER objective of Q = 10 requires the machine to be routinely operated at a nominal current Ip of 15 MA, and at full toroidal field BT of 5.3 T. This paper analyses the capabilities of the poloidal field (PF) system (including the central solenoid) of ITER against realistic full current plasma scenarios. An exploration of the ITER operational space for the 15 and 17 MA inductive scenario is carried out. An extensive analysis includes the evaluation of margins for the closed loop shape control action. The overall results of this analysis indicate that the control of a 15 MA plasma in ITER is likely to be adequate in the range of li 0.7–0.9 whereas, for a 17 MA plasma, control capabilities are strongly reduced. The ITER operational space, provided by the reference pre-2008 PF system, was rather limited if compared to the range of parameters normally observed in present experiment. Proposals for increasing the current and field limits on PF2, PF5 and PF6, adjustment on the number of turns in some of the PF coils, changes to the divertor dome geometry, to the conductor of PF6 to Nb3Sn, moving PF6 radially and/or vertically are described and evaluated in the paper. Some of them have been included in 2008 ITER revised configuration.
  Fusion Engineering and Design.
• Source

  Available from: A. Portone

  Article: Development of ITER 15 MA ELMy H-mode Inductive Scenario

  C.E. Kessel, D Campbell, Y. Gribov, G. Saibene, G. Ambrosino, T. Casper, M. Cavinato, H. Fujieda, R. Hawryluk, L. D. Horton, [......], M Mattei, I. Nunes, V. Parail, A. Polevoi, A. Portone, R. Sartori, A. C. C. Sips, P. R. Thomas, A. Welander, J. Wesley
  Fusion Energy 2008, International Atomic Energy Agency (2009).