TY - JOUR
T1 - Protecting ITER walls
T2 - Fast ion power loads in 3D magnetic field
AU - Kurki-Suonio, T.
AU - Sarkimaki, K.
AU - Akaslompolo, S.
AU - Varje, J.
AU - Liu, Y.
AU - Sipila, S.
AU - Asunta, O.
AU - Hirvijoki, E.
AU - Snicker, A.
AU - Terava, J.
AU - Cavinato, M.
AU - Gagliardi, M.
AU - Parail, V.
AU - Saibene, G.
PY - 2017/1
Y1 - 2017/1
N2 - The fusion alpha and beam ion with steady-state power loads in all four main operating scenarios of ITER have been evaluated by the ASCOT code. For this purpose, high-fidelity magnetic backgrounds were reconstructed, taking into account even the internal structure of the ferritic inserts and tritium breeding modules (TBM). The beam ions were found to be almost perfectly confined in all scenarios, and only the so-called hybrid scenario featured alpha loads reaching 0.5 MW due to its more triangular plasma. The TBMs were not found to jeopardize the alpha confinement, nor cause any hot spots. Including plasma response did not bring dramatic changes to the load. The ELM control coils (ECC) were simulated in the baseline scenario and found to seriously deteriorate even the beam confinement. However, the edge perturbation in this case is so large that the sources have to be re-evaluated with plasma profiles that take into account the ECC perturbation.
AB - The fusion alpha and beam ion with steady-state power loads in all four main operating scenarios of ITER have been evaluated by the ASCOT code. For this purpose, high-fidelity magnetic backgrounds were reconstructed, taking into account even the internal structure of the ferritic inserts and tritium breeding modules (TBM). The beam ions were found to be almost perfectly confined in all scenarios, and only the so-called hybrid scenario featured alpha loads reaching 0.5 MW due to its more triangular plasma. The TBMs were not found to jeopardize the alpha confinement, nor cause any hot spots. Including plasma response did not bring dramatic changes to the load. The ELM control coils (ECC) were simulated in the baseline scenario and found to seriously deteriorate even the beam confinement. However, the edge perturbation in this case is so large that the sources have to be re-evaluated with plasma profiles that take into account the ECC perturbation.
KW - 3-dimensional wall
KW - fast ion confinement
KW - ITER power loads
KW - non-axisymmetric magnetic field
KW - TBM
KW - test blanket modules
UR - http://www.scopus.com/inward/record.url?scp=85006170192&partnerID=8YFLogxK
U2 - 10.1088/0741-3335/59/1/014013
DO - 10.1088/0741-3335/59/1/014013
M3 - Article
AN - SCOPUS:85006170192
SN - 0741-3335
VL - 59
JO - Plasma Physics and Controlled Fusion
JF - Plasma Physics and Controlled Fusion
IS - 1
M1 - 014013
ER -
