2007
DOI: 10.1063/1.2739422
|View full text |Cite
|
Sign up to set email alerts
|

On heat loading, novel divertors, and fusion reactors

Abstract: The limited thermal power handling capacity of the standard divertors (used in current as well as projected tokamaks) is likely to force extremely high (∼90%) radiation fractions frad in tokamak fusion reactors that have heating powers considerably larger than ITER [D. J. Campbell, Phys. Plasmas 8, 2041 (2001)]. Such enormous values of necessary frad could have serious and debilitating consequences on the core confinement, stability, and dependability for a fusion power reactor, especially in reactors with Int… Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1
1
1
1

Citation Types

3
160
0

Year Published

2009
2009
2023
2023

Publication Types

Select...
9
1

Relationship

1
9

Authors

Journals

citations
Cited by 161 publications
(163 citation statements)
references
References 56 publications
3
160
0
Order By: Relevance
“…)(%$AH$-"D$,(13%H-'E-1D)%('%*-$1($% 1871,*$8%E$'D$(-"$)%',%*.--$,(%('#1D1#)%M)$$%="ECUNb%>62 U] /%S9>F UU/UV %1,8%Q;;;Q UW % ",%V]]a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…”
Section: @A))@$and-+/b(and'+$)) )mentioning
confidence: 99%
“…)(%$AH$-"D$,(13%H-'E-1D)%('%*-$1($% 1871,*$8%E$'D$(-"$)%',%*.--$,(%('#1D1#)%M)$$%="ECUNb%>62 U] /%S9>F UU/UV %1,8%Q;;;Q UW % ",%V]]a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…”
Section: @A))@$and-+/b(and'+$)) )mentioning
confidence: 99%
“…252 The q div, peak is reduced from 8 MW/m 2 to 2 MW/m 2 by increasing f exp from 10 to 40. The ideas for divertor heat flux mitigation through expanding the divertor flux include the snow-flake divertor (SFD) 253 and the X-divertor, 254,255 which are based on additional field null points close to the usual single null configuration of a conventional divertor. The multiple field nulls make the field null size larger, and cause greater field null expansion in the null region.…”
Section: Heat Flux Mitigation By Flux Expansionmentioning
confidence: 99%
“…An encouraging conclusion from this analysis is that if there is radial thermal diffusion along the field lines distant from the midplane, concepts such as the X-divertor 17 , Snowflake divertor 18 and particularly Super-X divertor 4 may offer an enhanced opportunity for thermal diffusion to contribute to heat flux dispersion, as a complement to the magnetic flux expansion central to these designs.…”
Section: Discussionmentioning
confidence: 86%