TY - JOUR
T1 - A control method of divertor plasma start-up assisted by tritium-ratio control for Demo-CREST
AU - Hiwatari, R.
AU - Okano, K.
AU - Ishida, M.
AU - Maeki, K.
AU - Hatayama, A.
AU - Ogawa, Y.
AU - Nakamura, M.
N1 - Funding Information:
This work was supported by the Ministry of Education, Culture, Sports, Science and Technology grant-in-aid for Young Scientists (B) 21760703 .
PY - 2011/10
Y1 - 2011/10
N2 - In this paper, core plasma operation flexibility by the tritium-ratio(T-ratio) control is proposed in order to control the fusion power keeping a high plasma density for the divetor heat-handling during the commissioning phase. The operational space of the core plasma for the Demo-CREST concept is expanded to the high density region by reducing T-ratio. Especially, the expansion of operation space for the low beta operation is large. For such operation expansion, the critical parameter is the confinement improvement factor HH, and a high HH similar to that of the ITER steady state (ITER-SS) operation is required for Demo-CREST. The resultant condition of the SOL density and the impurity radiation power required for the divertor heat load less than 10 MW/m2 is analyzed, and those operation conditions for the initial operation point of the fusion power 0 MW during the commissioning phase are found to be similar to those of the ITER-SS operation.
AB - In this paper, core plasma operation flexibility by the tritium-ratio(T-ratio) control is proposed in order to control the fusion power keeping a high plasma density for the divetor heat-handling during the commissioning phase. The operational space of the core plasma for the Demo-CREST concept is expanded to the high density region by reducing T-ratio. Especially, the expansion of operation space for the low beta operation is large. For such operation expansion, the critical parameter is the confinement improvement factor HH, and a high HH similar to that of the ITER steady state (ITER-SS) operation is required for Demo-CREST. The resultant condition of the SOL density and the impurity radiation power required for the divertor heat load less than 10 MW/m2 is analyzed, and those operation conditions for the initial operation point of the fusion power 0 MW during the commissioning phase are found to be similar to those of the ITER-SS operation.
KW - Commissioning operation
KW - Demo-CREST
KW - Demonstration reactor
KW - Divertor plasma
KW - Tritium ratio control
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U2 - 10.1016/j.fusengdes.2011.03.041
DO - 10.1016/j.fusengdes.2011.03.041
M3 - Article
AN - SCOPUS:80054074555
SN - 0920-3796
VL - 86
SP - 1099
EP - 1102
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
IS - 6-8
ER -