40:
20:
32:
142:, which is a small piece of material that projects a short distance into the outer edge of the main plasma confinement area. Ions from the fuel that are travelling outwards strike the limiter, thereby protecting the walls of the chamber from this damage. However, the problems with material being deposited into the fuel remained; the limiter simply changed where that material was coming from.
862:
237:(LHD), utilizes large helical coils to create a diverting field. This design permits adjustment of the stochastic layer size, situated between the confined plasma volume and the field lines ending on the divertor plate. However, the compatibility of the Helical Divertor with stellarators optimized for
149:
pull the lower edge of the plasma to create a small region where the outer edge of the plasma, the "Scrape-Off Layer" (SOL), hits a limiter-like plate. The divertor improves on the limiter in several ways, mainly because modern reactors try to create plasmas with D-shaped cross-sections ("elongation"
248:
provides an alternative design for optimized stellarators with significant bootstrap currents. This approach leverages sharp "ridges" on the plasma boundary to channel flux. The bootstrap currents modify the shape, not the location, of these ridges, providing an effective channeling mechanism. This
110:
being created and left in the fuel (the so-called "fusion ash"). These impurities were responsible for the loss of heat, and caused other effects that made it more difficult to keep the reaction going. The divertor was proposed as a solution to this problem. Operating on the same principle as a
252:
Given the complexity of the design of stellarator divertors, compared to their two-dimensional tokamak counterparts, a thorough understanding of their performance is crucial in stellarator optimization. The experiments with divertors in the W7-X and LHD have shown promising results and provide
225:
stellarator. The magnetic island chain in the plasma edge can control plasma fueling. Despite some challenges, the island divertor concept has demonstrated great potential for managing power and particle exhaust in fusion reactors, and further research could lead to more efficient and reliable
122:
When early long-shot reactors started to appear in the 1970s, a serious practical problem emerged. No matter how tightly constrained, plasma continued to leak out of the main confinement area, striking the walls of the reactor core and causing problems. A major concern was
70:
which separates the confined plasma from the material surface of the device. The plasma particles which diffuse across the boundary of the confined region are diverted by the open, wall-intersecting magnetic field lines to wall structures which are called the
253:
valuable insights for future improvements in shape and performance. Furthermore, the advent of non-resonant divertors offers an exciting path forward for quasi-symmetric stellarators and other configurations not optimized for minimizing plasma currents.
221:, for managing power and particle exhaust. The island divertor has shown success in accessing and stabilizing detached scenarios and has demonstrated reliable heat flux and detachment control with hydrogen gas injection, and impurity seeding in the
75:, usually remote from the confined plasma. The magnetic divertor extracts heat and ash produced by the fusion reaction, minimizes plasma contamination, and protects the surrounding walls from thermal and neutronic loads.
119:, colliding with some sort of absorber material, and depositing its energy as heat. Initially considered to be a device required for operational reactors, few early designs included a divertor.
173:
was built with divertor channels at both top and bottom. A divertor design called Super-X has been designed to reduce the heat density in the divertor by adopting a design resembling a funnel.
106:
The divertor was initially introduced during the earliest studies of fusion power systems in the 1950s. It was realized early on that successful fusion would result in heavier
355:
757:
193:), which allows the energy absorbing part of the divertor to be placed outside the plasma. The divertor configuration also makes it easier to obtain a more stable
662:"Overview of the results from divertor experiments with attached and detached plasmas at Wendelstein 7-X and their implications for steady-state operation"
554:
325:] T N Todd and C G Windsor, Progress in Magnetic Confinement Fusion Research, Contemporary Physics, 1998, volume 39, number 4, pages 255-282
604:
78:
The term divertor usually describes the magnetic configuration itself or the region between the confined plasma and the target. Sometimes
337:
309:
826:
391:
150:
and "triangularity") so the lower edge of the D is a natural location for the divertor. In modern examples the plates are replaced by
417:
796:
366:
903:
490:"Stable heat and particle flux detachment with efficient particle exhaust in the island divertor of Wendelstein 7-X"
605:"Impact of magnetic islands in the plasma edge on particle fueling and exhaust in the HSX and W7-X stellarators"
555:"First demonstration of radiative power exhaust with impurity seeding in the island divertor at Wendelstein 7-X"
145:
This led to the re-emergence of the divertor, as a device for protecting the reactor itself. In these designs,
927:
190:
51:
95:
896:
115:, the plasma passes through the divertor region where heavier ions are flung out of the fuel mass by
710:
91:
432:
238:
198:
334:
313:
922:
803:
194:
823:
128:
889:
769:
722:
673:
616:
569:
501:
444:
395:
234:
162:
465:
8:
154:
metal, which better captures the ions and causes less cooling when it enters the plasma.
773:
734:
726:
677:
620:
573:
505:
448:
738:
711:"Initial experiments towards edge plasma control with a closed helical divertor in LHD"
691:
642:
585:
535:
470:
201:
in the divertor faces significantly different stresses compared to the majority of the
742:
695:
646:
637:
589:
539:
527:
522:
456:
116:
112:
474:
869:
777:
730:
681:
632:
624:
577:
517:
509:
460:
452:
877:
847:
830:
341:
138:
During the 1980s it became common for reactors to include a feature known as the
44:
39:
19:
842:
287:
873:
686:
661:
581:
513:
262:
189:
tokamak. In this configuration, the particles escape through a magnetic "gap" (
132:
781:
916:
170:
24:
392:"MIT Plasma Science & Fusion Center: Research>alcator>information"
797:"Progress in Divertor and Edge Transport Research for Stellarator Plasmas"
214:
67:
31:
217:, low-order magnetic islands can be used to form a divertor volume, the
418:"First results from UK tokamak offers a STEP towards commercial fusion"
202:
124:
628:
531:
489:
433:"Physics of island divertors as highlighted by the example of W7-AS"
249:
design, although promising, has not been experimentally tested yet.
151:
63:
146:
35:
Divertor design for K-DEMO, a planned future tokamak experiment
27:
showing the lower divertor channel at the bottom of the torus
267:
222:
158:
87:
861:
356:"Tokamak Divertor System Concept and the Design for ITER"
107:
824:
Snowflake and the multiple divertor concepts. March 2016
165:, the lowest region of the torus is configured as a
135:'s wall metal to flow into the fuel and to cool it.
552:
914:
708:
659:
897:
181:A tokamak featuring a divertor is known as a
602:
16:Magnetic confinement fusion device component
487:
127:in reactors with higher power and particle
86:are used interchangeably. For example, the
904:
890:
430:
90:divertor refers to the heavily engineered
685:
636:
521:
464:
208:
38:
30:
18:
353:
62:is a magnetic field configuration of a
915:
755:
794:
856:
176:
660:Jakubowksi, M; et al. (2021).
347:
13:
817:
553:Effenberg, F; et al. (2019).
14:
939:
836:
795:Bader, Aaron (December 6, 2018).
709:Morisaki, T; et al. (2013).
860:
603:Stephey, L; et al. (2018).
488:Schmitz, O; et al. (2021).
354:Stoafer, Chris (14 April 2011).
161:and the latest configuration of
788:
749:
702:
653:
596:
94:designed to handle the intense
546:
481:
466:11858/00-001M-0000-0027-0DC4-8
424:
410:
384:
328:
302:
280:
1:
735:10.1088/0029-5515/53/6/063014
431:Feng, Y; et al. (2006).
288:"RF Absorbers material types"
273:
876:. You can help Knowledge by
407:retrieved September 11, 2012
7:
256:
131:, which caused ions of the
52:magnetic confinement fusion
10:
944:
855:
457:10.1088/0029-5515/46/8/006
290:. www.masttechnologies.com
101:
782:10.1017/S0022377815001373
762:Journal of Plasma Physics
638:21.11116/0000-0001-6AE2-9
523:21.11116/0000-0007-A4DC-8
340:January 10, 2014, at the
226:operation in the future.
687:10.1088/1741-4326/ac1b68
582:10.1088/1741-4326/ab32c4
514:10.1088/1741-4326/abb51e
335:"Limiters and Divertors"
96:plasma-wall interactions
92:plasma-facing components
872:–related article is a
239:neoclassical transport
199:plasma facing material
187:divertor configuration
60:diverted configuration
47:
36:
28:
756:Boozer, A.H. (2015).
363:www.apam.columbia.edu
246:non-resonant divertor
233:, as employed in the
209:Stellarator divertors
42:
34:
22:
928:Plasma physics stubs
758:"Stellarator design"
235:Large Helical Device
163:Joint European Torus
774:2015JPlPh..81f5106B
727:2013NucFu..53f3014M
678:2021NucFu..61j6003J
621:2018PhPl...25f2501S
574:2019NucFu..59j6020E
506:2021NucFu..61a6026S
449:2006NucFu..46..807F
241:remains uncertain.
829:2016-03-29 at the
609:Physics of Plasmas
197:of operation. The
48:
37:
29:
885:
884:
629:10.1063/1.5026324
177:Tokamak divertors
117:centrifugal force
113:mass spectrometer
935:
906:
899:
892:
864:
857:
811:
810:
808:
802:. Archived from
801:
792:
786:
785:
768:(6): 515810606.
753:
747:
746:
706:
700:
699:
689:
657:
651:
650:
640:
600:
594:
593:
559:
550:
544:
543:
525:
485:
479:
478:
468:
428:
422:
421:
414:
408:
406:
404:
403:
394:. Archived from
388:
382:
381:
379:
377:
371:
365:. Archived from
360:
351:
345:
332:
326:
324:
322:
321:
312:. Archived from
306:
300:
299:
297:
295:
284:
231:helical divertor
183:divertor tokamak
73:divertor targets
943:
942:
938:
937:
936:
934:
933:
932:
913:
912:
911:
910:
853:
839:
831:Wayback Machine
820:
818:Further reading
815:
814:
806:
799:
793:
789:
754:
750:
707:
703:
658:
654:
601:
597:
557:
551:
547:
486:
482:
429:
425:
416:
415:
411:
401:
399:
390:
389:
385:
375:
373:
369:
358:
352:
348:
342:Wayback Machine
333:
329:
319:
317:
308:
307:
303:
293:
291:
286:
285:
281:
276:
259:
219:island divertor
211:
179:
104:
80:divertor target
17:
12:
11:
5:
941:
931:
930:
925:
909:
908:
901:
894:
886:
883:
882:
870:plasma physics
865:
851:
850:
845:
838:
837:External links
835:
834:
833:
819:
816:
813:
812:
809:on 2023-07-26.
787:
748:
701:
672:(10): 106003.
652:
595:
568:(10): 106020.
545:
480:
443:(8): 807–819.
423:
420:. 25 May 2021.
409:
383:
346:
327:
301:
278:
277:
275:
272:
271:
270:
265:
263:Nuclear fusion
258:
255:
210:
207:
178:
175:
133:vacuum chamber
103:
100:
15:
9:
6:
4:
3:
2:
940:
929:
926:
924:
921:
920:
918:
907:
902:
900:
895:
893:
888:
887:
881:
879:
875:
871:
866:
863:
859:
858:
854:
849:
846:
844:
841:
840:
832:
828:
825:
822:
821:
805:
798:
791:
783:
779:
775:
771:
767:
763:
759:
752:
744:
740:
736:
732:
728:
724:
721:(6): 063014.
720:
716:
712:
705:
697:
693:
688:
683:
679:
675:
671:
667:
663:
656:
648:
644:
639:
634:
630:
626:
622:
618:
615:(6): 062501.
614:
610:
606:
599:
591:
587:
583:
579:
575:
571:
567:
563:
556:
549:
541:
537:
533:
529:
524:
519:
515:
511:
507:
503:
500:(1): 016026.
499:
495:
491:
484:
476:
472:
467:
462:
458:
454:
450:
446:
442:
438:
434:
427:
419:
413:
398:on 2012-06-17
397:
393:
387:
372:on 2013-12-11
368:
364:
357:
350:
343:
339:
336:
331:
316:on 2014-01-10
315:
311:
305:
289:
283:
279:
269:
266:
264:
261:
260:
254:
250:
247:
242:
240:
236:
232:
227:
224:
220:
216:
206:
204:
200:
196:
192:
188:
184:
174:
172:
171:Alcator C-Mod
168:
164:
160:
155:
153:
148:
143:
141:
136:
134:
130:
126:
120:
118:
114:
109:
99:
97:
93:
89:
85:
81:
76:
74:
69:
65:
61:
57:
53:
46:
41:
33:
26:
25:Alcator C-Mod
21:
923:Fusion power
878:expanding it
867:
852:
804:the original
790:
765:
761:
751:
718:
715:Nucl. Fusion
714:
704:
669:
666:Nucl. Fusion
665:
655:
612:
608:
598:
565:
562:Nucl. Fusion
561:
548:
497:
494:Nucl. Fusion
493:
483:
440:
437:Nucl. Fusion
436:
426:
412:
400:. Retrieved
396:the original
386:
376:11 September
374:. Retrieved
367:the original
362:
349:
330:
318:. Retrieved
314:the original
304:
292:. Retrieved
282:
251:
245:
243:
230:
228:
218:
215:stellarators
212:
186:
182:
180:
166:
156:
144:
139:
137:
129:flux density
121:
105:
83:
79:
77:
72:
59:
55:
49:
43:Divertor of
23:Interior of
68:stellarator
917:Categories
402:2012-09-11
320:2014-01-10
274:References
203:first wall
191:separatrix
125:sputtering
98:foreseen.
848:Divertors
743:122537627
696:237408135
647:125652747
590:199132000
540:225288529
294:30 August
843:Limiters
827:Archived
475:62893155
338:Archived
310:"Fusrev"
257:See also
169:, while
167:divertor
84:divertor
56:divertor
770:Bibcode
723:Bibcode
674:Bibcode
617:Bibcode
570:Bibcode
532:1814444
502:Bibcode
445:Bibcode
152:lithium
147:magnets
140:limiter
102:History
64:tokamak
45:COMPASS
741:
694:
645:
588:
538:
530:
473:
344:, EFDA
195:H-mode
868:This
807:(PDF)
800:(PDF)
739:S2CID
692:S2CID
643:S2CID
586:S2CID
558:(PDF)
536:S2CID
471:S2CID
370:(PDF)
359:(PDF)
66:or a
874:stub
528:OSTI
378:2012
296:2015
268:ITER
244:The
229:The
223:W7-X
159:ITER
108:ions
88:ITER
82:and
54:, a
778:doi
731:doi
682:doi
633:hdl
625:doi
578:doi
518:hdl
510:doi
461:hdl
453:doi
213:In
185:or
157:In
58:or
50:In
919::
776:.
766:81
764:.
760:.
737:.
729:.
719:53
717:.
713:.
690:.
680:.
670:61
668:.
664:.
641:.
631:.
623:.
613:25
611:.
607:.
584:.
576:.
566:59
564:.
560:.
534:.
526:.
516:.
508:.
498:61
496:.
492:.
469:.
459:.
451:.
441:46
439:.
435:.
361:.
205:.
905:e
898:t
891:v
880:.
784:.
780::
772::
745:.
733::
725::
698:.
684::
676::
649:.
635::
627::
619::
592:.
580::
572::
542:.
520::
512::
504::
477:.
463::
455::
447::
405:.
380:.
323:.
298:.
Text is available under the Creative Commons Attribution-ShareAlike License. Additional terms may apply.
