TY - JOUR
T1 - Numerical analyses of baseline JT-60SA design concepts with the COREDIV code
AU - Zagórski, R.
AU - Gałazka, K.
AU - Ivanova-Stanik, I.
AU - Stȩpniewski, W.
AU - Garzotti, L.
AU - Giruzzi, G.
AU - Neu, R.
AU - Romanelli, M.
N1 - Publisher Copyright:
© 2017 Institute of Plasma Physics and Laser Microfusion.
PY - 2017/5/3
Y1 - 2017/5/3
N2 - JT-60SA reference design scenarios at high (#3) and low (#2) density have been analyzed with the help of the self-consistent COREDIV code. Simulations results for a standard C wall and full W wall have been compared in terms of the influence of impurities, both intrinsic (C, W) and seeded (N, Ar, Ne, Kr), on the radiation losses and plasma parameters. For scenario #3 in a C environment, the regime of detachment on divertor plates can be achieved with N or Ne seeding, whereas for the low density and high power scenario (#2), the C and seeding impurity radiation does not effectively reduce power to the targets. In this case, only an increase of either average density or edge density together with Kr seeding might help to develop conditions with strong radiation losses and semi-detached conditions in the divertor. The calculations show that, in the case of a W divertor, the power load to the plate is mitigated by seeding and the central plasma dilution is smaller compared to the C divertor. For the high density case (#3) with Ne seeding, operation in full detachment mode is predicted. Ar seems to be an optimal choice for the low-density high-power scenario #2, showing a wide operating window, whereas Ne leads to high plasma dilution at high seeding levels albeit not achieving semi-detached conditions in the divertor.
AB - JT-60SA reference design scenarios at high (#3) and low (#2) density have been analyzed with the help of the self-consistent COREDIV code. Simulations results for a standard C wall and full W wall have been compared in terms of the influence of impurities, both intrinsic (C, W) and seeded (N, Ar, Ne, Kr), on the radiation losses and plasma parameters. For scenario #3 in a C environment, the regime of detachment on divertor plates can be achieved with N or Ne seeding, whereas for the low density and high power scenario (#2), the C and seeding impurity radiation does not effectively reduce power to the targets. In this case, only an increase of either average density or edge density together with Kr seeding might help to develop conditions with strong radiation losses and semi-detached conditions in the divertor. The calculations show that, in the case of a W divertor, the power load to the plate is mitigated by seeding and the central plasma dilution is smaller compared to the C divertor. For the high density case (#3) with Ne seeding, operation in full detachment mode is predicted. Ar seems to be an optimal choice for the low-density high-power scenario #2, showing a wide operating window, whereas Ne leads to high plasma dilution at high seeding levels albeit not achieving semi-detached conditions in the divertor.
KW - JT-60SA
KW - impurity seeding
KW - tokamak modelling
UR - http://www.scopus.com/inward/record.url?scp=85019426588&partnerID=8YFLogxK
U2 - 10.1088/1741-4326/aa6602
DO - 10.1088/1741-4326/aa6602
M3 - Article
AN - SCOPUS:85019426588
SN - 0029-5515
VL - 57
JO - Nuclear Fusion
JF - Nuclear Fusion
IS - 6
M1 - 066035
ER -