| Contributors: |
Carvalho, I. S.; Giroud, C.; King, D. B.; Keeling, D. L.; Frassinetti, L.; Pitts, R. A.; Wiesen, S.; Pucella, G.; Kappatou, A.; Vianello, N.; Wischmeier, M.; Rimini, F.; Baruzzo, M.; Maslov, M.; Sos, M.; Litaudon, X.; Henriques, R. B.; Kirov, K.; Perez von Thun, C.; Sun, H. J.; Lennholm, M.; Mitchell, J.; Parrot, A.; Bernardo, J.; Zerbini, M.; Coffey, I.; Collie, K.; Fontdecaba, J. M.; Hawkes, N.; Huang, Z.; Jepu, I.; Kos, D.; Lawson, K.; Litherland-Smith, E.; Meigs, A.; Olde, C.; Patel, A.; Piron, L.; Poradzinski, M. P.; Stancar, Z.; Taylor, D.; Alessi, E.; Balboa, I.; Boboc, A.; Bakes, S.; Brix, M.; De la Cal, E.; Carvalho, P.; Chomiczewska, A.; Ghani, Z.; Giovannozzi, E.; Foster, J.; Huber, A.; Karhunen, J.; Kowalska-Strzeciwilk, E.; Maddock, J.; Matthews, J.; Menmuir, S.; Mikszuta, K.; Morales-Bianchetti, R. B.; Pawelec, E.; Petravich, G.; Pinto, E.; Voldiner, I.; Sergienko, G.; Silburn, S.; Svodoba, J.; Tomes, M.; Thomas, B.; Tookey, A.; Zayachuk, Y.; Valovic, M.; Widdowson, A.; Xiang, L.; Auriemma, F.; Innocente, P.; Gabriellini, S.; Mariani, A.; Marin, M.; Predebon, I.; Thrysoe, A.; Zotta, V. K. |
| Description: |
The ITER baseline scenario [1] defined as the first target for ITER deuterium-tritium (DT) operation consists on an inductive scenario at 15MA, 5.3T, high triangularity (≈0.45), q95≈3, Q=10 expected to be achieved with H98(y,2)=1, fGW=0.86, βp=0.86, and e,ped*=0.01 for a duration greater than 300s. The integrity of the divertor requires the heat load to be maintined below 10MW.m-2 , and for this, neon impurity seeding is required to achieve a partially detached divertor state. The challenge in achieving this integrated scenario in ITER is to reduce the power load whislt maintaining sufficient impurity compression at the divertor, and midplane in order to keep the impurity content in the core plasma within an acceptable limit for the required fusion gain. Over the past years, JET has carried out core-edge integration studies [2] dedicated to understand how the integrated scenario of ITER would work in the so-called JET ITER baseline plasmas with the following characteristics: high-triangularity (=0.35- 0.38), with divertor configuration with the inner and outer leg on the vertical targets, closer to the ITER divertor and optimal for better detachment, see figure 1. The previously best demonstration of an integrated ITER-baseline scenario with neon seeding at JET was obtained at 2.5MA/2.7T, H98(y,2) =0.9, N=2.2, av =0.37, fGW=0.7, frad=0.86, Zeff=2.7, PNBI=29MW, PICRH=5MW with deuterium (D) gas rate of 3.6x1022 el.s-1 and no ELMs (pulse #97490) [2][3]. Machine size and high temperature was demonstrated to be key to maintain impurities in the divertor where it is aimed for them to radiate [4][5][6]. Consequently, JET the closest tokamak in size to ITER amongst current devices is best positioned to address the core-edge integration issues. Although, we note that JET cannot reach the same neon compression, therefore, in semidetachment state some radiation is located near the x-point (see figure 5), unlike the expectations for ITER where most radiation is expected to be below x-point [5]. The core-edge ... |