Abstract
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.
| Original language | English |
|---|---|
| Pages (from-to) | 1099-1102 |
| Number of pages | 4 |
| Journal | Fusion Engineering and Design |
| Volume | 86 |
| Issue number | 6-8 |
| DOIs | |
| Publication status | Published - 2011 Oct |
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Keywords
- Commissioning operation
- Demo-CREST
- Demonstration reactor
- Divertor plasma
- Tritium ratio control
ASJC Scopus subject areas
- Nuclear Energy and Engineering
- Materials Science(all)
- Civil and Structural Engineering
- Mechanical Engineering
Cite this
A control method of divertor plasma start-up assisted by tritium-ratio control for Demo-CREST. / Hiwatari, R.; Okano, Kunihiko; Ishida, M.; Maeki, K.; Hatayama, Akiyoshi; Ogawa, Y.; Nakamura, M.
In: Fusion Engineering and Design, Vol. 86, No. 6-8, 10.2011, p. 1099-1102.Research output: Contribution to journal › Article
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TY - JOUR
T1 - A control method of divertor plasma start-up assisted by tritium-ratio control for Demo-CREST
AU - Hiwatari, R.
AU - Okano, Kunihiko
AU - Ishida, M.
AU - Maeki, K.
AU - Hatayama, Akiyoshi
AU - Ogawa, Y.
AU - Nakamura, M.
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
UR - http://www.scopus.com/inward/record.url?scp=80054074555&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=80054074555&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2011.03.041
DO - 10.1016/j.fusengdes.2011.03.041
M3 - Article
AN - SCOPUS:80054074555
VL - 86
SP - 1099
EP - 1102
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
IS - 6-8
ER -