Abstract
The divertor configuration defines the power exhaust capabilities of DEMO as one of the major key design parameters and sets a number of requirements on the tokamak layout, including port sizes, poloidal field coil positions, and size of toroidal field coils. It also requires a corresponding configuration of plasma-facing components (PFCs) and a remote handling scheme to be able to handle the cassettes and associated in-vessel components (IVC) the configuration requires. There is a risk that the baseline ITER-like single-null (SN) divertor configuration cannot meet the PFC technology limits regarding power exhaust and first wall protection while achieving the target plasma performance requirements of DEMO or a future fusion power plant. Alternative magnetic configurations – double-null, snowflake, X-, and super-X – exist and potentially offer solutions to these risks and a route to achievable power handling in DEMO. But these options impose significant changes on machine architecture, increase the machine complexity and affect remote handling and plasma physics and so an integrated approach must be taken to assessing the feasibility of these options. In this paper we describe the work programme to assess the requirements for incorporating these configurations into DEMO.
| Original language | English |
|---|---|
| Pages (from-to) | 2281-2284 |
| Number of pages | 4 |
| Journal | Fusion Engineering and Design |
| Volume | 146 |
| Issue number | Part B |
| DOIs | |
| Publication status | Published - 1 Sep 2019 |
| MoE publication type | A1 Journal article-refereed |
Fingerprint
Keywords
- DEMO
- Fusion power plant
- System modelling
- Systems studies
- Technology choices
Cite this
}
Engineering and integration risks arising from advanced magnetic divertor configurations. / Kembleton, R. (Corresponding Author); Federici, G.; Ambrosino, R.; Maviglia, F.; Siccinio, M.; Reimerdes, H.; Ha, S.; Merriman, S.; Bachmann, C.; Suiko, M.
In: Fusion Engineering and Design, Vol. 146, No. Part B, 01.09.2019, p. 2281-2284.Research output: Contribution to journal › Article › Scientific › peer-review
TY - JOUR
T1 - Engineering and integration risks arising from advanced magnetic divertor configurations
AU - Kembleton, R.
AU - Federici, G.
AU - Ambrosino, R.
AU - Maviglia, F.
AU - Siccinio, M.
AU - Reimerdes, H.
AU - Ha, S.
AU - Merriman, S.
AU - Bachmann, C.
AU - Suiko, M.
PY - 2019/9/1
Y1 - 2019/9/1
N2 - The divertor configuration defines the power exhaust capabilities of DEMO as one of the major key design parameters and sets a number of requirements on the tokamak layout, including port sizes, poloidal field coil positions, and size of toroidal field coils. It also requires a corresponding configuration of plasma-facing components (PFCs) and a remote handling scheme to be able to handle the cassettes and associated in-vessel components (IVC) the configuration requires. There is a risk that the baseline ITER-like single-null (SN) divertor configuration cannot meet the PFC technology limits regarding power exhaust and first wall protection while achieving the target plasma performance requirements of DEMO or a future fusion power plant. Alternative magnetic configurations – double-null, snowflake, X-, and super-X – exist and potentially offer solutions to these risks and a route to achievable power handling in DEMO. But these options impose significant changes on machine architecture, increase the machine complexity and affect remote handling and plasma physics and so an integrated approach must be taken to assessing the feasibility of these options. In this paper we describe the work programme to assess the requirements for incorporating these configurations into DEMO.
AB - The divertor configuration defines the power exhaust capabilities of DEMO as one of the major key design parameters and sets a number of requirements on the tokamak layout, including port sizes, poloidal field coil positions, and size of toroidal field coils. It also requires a corresponding configuration of plasma-facing components (PFCs) and a remote handling scheme to be able to handle the cassettes and associated in-vessel components (IVC) the configuration requires. There is a risk that the baseline ITER-like single-null (SN) divertor configuration cannot meet the PFC technology limits regarding power exhaust and first wall protection while achieving the target plasma performance requirements of DEMO or a future fusion power plant. Alternative magnetic configurations – double-null, snowflake, X-, and super-X – exist and potentially offer solutions to these risks and a route to achievable power handling in DEMO. But these options impose significant changes on machine architecture, increase the machine complexity and affect remote handling and plasma physics and so an integrated approach must be taken to assessing the feasibility of these options. In this paper we describe the work programme to assess the requirements for incorporating these configurations into DEMO.
KW - DEMO
KW - Fusion power plant
KW - System modelling
KW - Systems studies
KW - Technology choices
UR - http://www.scopus.com/inward/record.url?scp=85063572386&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2019.03.172
DO - 10.1016/j.fusengdes.2019.03.172
M3 - Article
AN - SCOPUS:85063572386
VL - 146
SP - 2281
EP - 2284
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
IS - Part B
ER -