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PRODID:-//Memento EPFL//
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SUMMARY:Towards an Assessment of Alternative Divertor Solutions for DEMO
DTSTART:20150506T103000
DTEND:20150506T113000
DTSTAMP:20260427T231117Z
UID:c0feda9fe8efd6fee50deb7dbba68641f5d8c39dee0c053c346e9a11
CATEGORIES:Conferences - Seminars
DESCRIPTION:Dr. Holger Reimerdes\, EPFL-CRPP\, for the WPDTT1 EUROfusion p
 roject\nTo mitigate the risk that the conventional divertor solution adopt
 ed for ITER\, which is based on a single-null magnetic configuration and t
 ungsten (W) targets\, will not extrapolate to a fusion power plant\, the E
 uropean fusion consortium (EUROfusion) is assessing alternative divertor s
 olutions. Considered alternatives include non-conventional configurations 
 and the use of liquid metals (LMs) as divertor armour. Their performance a
 nd costs will be compared to those of a conservative DEMO design targeting
  500 MW of electric power with a major radius of 9 m\, a toroidal field of
  5.8 T and a plasma current of 20 MA.\nThe assessment of alternative confi
 gurations considers the snowflake divertor (SFD)\, the X divertor (XD) and
  the Super-X divertor (SXD). DEMO prototypes of these configurations have 
 been developed and are now optimised to minimise the required PF coil mass
 \, the volume enclosed by the TF coils\, the forces between coils and the 
 fraction of neutrons lost for breeding. Any increase of these costs over t
 he reference solution is weighed against predictions of the performance im
 provement with regard to access to and stability of operation in the detac
 hed regime and any increase of the power that can be radiated in the diver
 tor using state-of-the-art boundary models. The assessment of LM based div
 ertor solutions focuses on a heat conduction based capillary porous system
  (CPS)\, which is viewed as the least complex LM based solution. While the
  heat exhaust potential of such a solution faces similar challenges as W t
 argets\, key advantages are the in-situ repair of eroded material and pote
 ntially a greater tolerance for transient heat flux excursions. Materials 
 considered are lithium (Li)\, tin (Sn) or Li/Sn alloys and the assessment 
 includes a demonstration of a CPS solution including cooling and replenish
 ment in the FTU tokamak.\nUpon conclusion the assessment should identify a
 ny gaps that must be addressed before considering an alternative divertor 
 solution for DEMO.
LOCATION:PPB 019
STATUS:CONFIRMED
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