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Rencontre scientifique autour de la production de poussières dans les plasmas d’ITER. (vendredi 11 juillet, 10:30)

par Caroline CHAMPENOIS - publié le

séminaires pour spécialistes

vendredi 11 juillet, 10:30, service 322

À l’occasion d’une réunion de travail au PIIM, autour de l’érosion des parois et le transport des impuretés dans les réacteurs tels que ITER, vous êtes invités à assister aux deux séminaires suivants :

programme :

  • 10h30 : "Dust generation in ITER" par Richard Pitts(ITER Organization, Tungsten Divertor and Plasma-Wall Interactions Section)
  • 11h : "Dust, tritium retention and erosion diagnostics in ITER" par Gregory De Temmerman (ITER Organization, Tungsten Divertor and Plasma-Wall Interactions Section)

Contact pour cette réunion de travail : Cécile Arnas

Get the latest ITER news on http://www.iter.org/newsline/latest

Résumé des présentations :

"Dust generation in ITER" par Richard Pitts, Section Leader, Divertor and Plasma-Wall Interactions Section
Dust has long been recognized as potential issue for tokamak operation and safety when extrapolating to reactor-scale devices such as ITER. It figures prominently in the Preliminary Safety Case Report (RPrS), which was the basis for obtaining, in Nov. 2012, the Decree (no 2012-1248) from the French government for the creation of ITER as a Basic Nuclear Installation. In ITER, with its beryllium (Be) armoured main chamber walls and tungsten (W) divertor components, modelling indicates up to many tens of kg of dust might be generated in a given nuclear campaign. There are currently many unknowns concerning the degree to which this dust accumulation will pose an issue for plasma operation, but the quantity generated is not expected to exceed that allowed in the vacuum vessel from the safety point of view.
This presentation will provide a brief overview of the general erosion and migration pathways for impurities released by plasma-surface interaction in ITER and then present our current understanding of the likely dust creation rate, due both to steady state and transient plasma impact. These estimates are based on state-of-the-art impurity transport modelling, worst case transient impact parameters and extrapolation from observations in present devices, particularly from the JET tokamak, which has recently equipped itself with a Be first wall and W divertor, matching the material environment ITER will use.

Contact : richard.pitts_@_iter.org
ITER Organization, Building 72/401, POP, Science Division
Route de Vinon-sur-Verdon - CS 90 046 - 13067 St Paul Lez Durance Cedex – France
Phone : +33 4 42 17 65 12 - Mobile : +33 6 14 16 40 16

"Dust, tritium retention and erosion diagnostics in ITER" par Gregory De Temmerman, Coordinating Scientist Plasma Edge & PWI, Tungsten Divertor and Plasma-Wall Interactions Section
The ITER Licensing agreement imposes upper limits for the inventories of dust and tritium in the vacuum vessel. Dust creation and tritium retention are mainly driven by plasma-wall interactions. The recent decision to start ITER operations with a full tungsten divertor has motivated a recent review of the dust, erosion and tritium retention diagnostic suite which is foreseen in ITER. An international workshop was held in February 2014 at ITER Organization to review and adapt the measurement requirements of those diagnostics and adapt them to the full-W divertor situation.

This presentation will give a brief overview of the diagnostic systems foreseen for the measurements of material erosion and dust and tritium inventory, and will briefly discuss the status of the individual systems. Emphasis will be put on the current physics questions that still need to be answered to improve the dust and tritium inventory measurements.

Contact  : Gregory.detemmerman_@_iter.org
ITER Organization, Building 72/414, POP, Science Division
Route de Vinon-sur-Verdon - CS 90 046 - 13067 St Paul Lez Durance Cedex – France
Phone : +33 4 42 17 65 53

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