shape and geometry optimisation of iter plasma facing components

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ITPA meeting, Toronto W. Fundamenski 7/11/2006 TF-E Shape and geometry optimisation of ITER plasma facing components W.Fundamenski, K. Krieger, A. Loarte, G.F. Matthews, V. Philipps, T. Tanabe, and ITPA Divertor-SOL TG ITPA TG Groups to Consider: Divertor, Pedestal, Steady-State Implied Action for ITER design activity: Apply more rigorous design rules for the ITER PFCs both at the local level (surface shape, geometry of castellations/gaps, tolerances of tile alignment) and more generally (limiter geometry, arrangement of limiters and dump-plates). Aims: reduction of hot spots and T-inventory Systems Affected: First wall armour design (main) and first wall cooling components (other) Benefit to ITER: Wider safe operating space margins for wall and divertor. Longer plasma operation before reaching tritium in-vessel limit and reduced requirements for in-situ T-removal procedures. No drawbacks foreseen. ITER issue card PFC-3

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ITER issue card PFC-3. Shape and geometry optimisation of ITER plasma facing components W.Fundamenski, K. Krieger, A. Loarte, G.F. Matthews, V. Philipps, T. Tanabe, and ITPA Divertor-SOL TG. ITPA TG Groups to Consider: Divertor, Pedestal, Steady-State - PowerPoint PPT Presentation

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Page 1: Shape and geometry optimisation of ITER plasma facing components

ITPA meeting, Toronto W. Fundamenski 7/11/2006

TF-E

Shape and geometry optimisation of ITER plasma facing components

W.Fundamenski, K. Krieger, A. Loarte, G.F. Matthews, V. Philipps, T. Tanabe, and ITPA Divertor-SOL TG

ITPA TG Groups to Consider: Divertor, Pedestal, Steady-State

Implied Action for ITER design activity: Apply more rigorous design rules for the ITER PFCs both at the local level (surface shape, geometry of castellations/gaps, tolerances of tile alignment) and more generally (limiter geometry, arrangement of limiters and dump-plates).

Aims: reduction of hot spots and T-inventory

Systems Affected: First wall armour design (main) and first wall cooling components (other)

Benefit to ITER: Wider safe operating space margins for wall and divertor.Longer plasma operation before reaching tritium in-vessel limit and reduced requirements for in-situ T-removal procedures. No drawbacks foreseen.

ITER issue card PFC-3

Page 2: Shape and geometry optimisation of ITER plasma facing components

ITPA meeting, Toronto W. Fundamenski 7/11/2006

TF-EELM impact on first wall: wide IR view from JET

Page 3: Shape and geometry optimisation of ITER plasma facing components

ITPA meeting, Toronto W. Fundamenski 7/11/2006

TF-EHeat load reduction on leading edges

Consider the design of the ITER-like wall for JET (similar issues as in ITER)

Need for wide range of plasma configurations, high level of flexibility.

Formation of hot spots at leading edges can limit lifetime of first wall.

Excessive erosion at leading edges degrades the component life-time.

Need to minimise leading edges in the design of PFCs eg. macrobrushes and castellations

Flexibility might require additional, optimally shaped poloidal wall limiters separated by recessed wall areas.

Schedule Implication: May delay schedule due to additional effort (design, R&D,procurement). This can be minimised if new R&D could be avoided, eg. heat flux tests.

Cost Implication: significant. No estimate as yet.

Page 4: Shape and geometry optimisation of ITER plasma facing components

ITPA meeting, Toronto W. Fundamenski 7/11/2006

TF-EPort limiter assembly

Page 5: Shape and geometry optimisation of ITER plasma facing components

ITPA meeting, Toronto W. Fundamenski 7/11/2006

TF-ELimiter port plug

Page 6: Shape and geometry optimisation of ITER plasma facing components

ITPA meeting, Toronto W. Fundamenski 7/11/2006

TF-EPoloidal flux surfaces and limiter module

Page 7: Shape and geometry optimisation of ITER plasma facing components

ITPA meeting, Toronto W. Fundamenski 7/11/2006

TF-ERFHT limiter plate with castellations