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ITER Design Review

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18 poloidal bands of advanced standard modules ~100mm ... Watch This Space ! EUTFPWI Meeting 29-31/10/07 C.Lowry. EUTFPWI Meeting 29-31/10/07 C.Lowry ... – PowerPoint PPT presentation

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Title: ITER Design Review


1
ITER Design Review Decisions Taken
  • 5 Major Issues Identified
  • Blanket Redesign
  • Vertical Stability and Shape Control
  • ELM and RWM Coils
  • Hot Cell and Test Requirements
  • Tritium and Dust

2
Blanket Re-design
  • Main Issues with Blanket Design
  • Refinement of Power Handling Requirements
  • Installation and Remote Handling
  • Constraints
  • Keep vacuum vessel interfaces fixed
  • Minimise changes to the baseline design

3
Steady State Wall Loads
Parallel (?)
1
Perpendicular (-)
4
Wall Loads due to Off-normal events
Parallel (?)
1
Perpendicular (-)
5
Design Philosophy
Shape first wall to shadow exposed edges Improve
the hydraulic connector by providing larger
access hole Details
18 poloidal bands of advanced standard modules
100mm
Ports
8 or less degradation in power handling at upper
X-point
6
Concept Under Construction
Wall start-up is being considered, and first
indications are encouraging An in-vessel
detachable first wall has several advantages, and
is being pursued
7
Vertical Stabilisation and Plasma Position and
Shape Control
  • li1.1 SOF
  • 15 MA full k
  • Inward shift 9cm
  • Reference VS (6kV)

Instability growth time goes from 71ms ? 37ms
Outside control range, the plasma is vertically
unstable
G.Saibene
8
Vertical Stabilisation and Plasma Position and
Shape Control
  • Fast H-L transition (b loss in 1-2 s? IW contact
    for up to 5s) can lead to large loads on the
    inner wall

A.Loarte
9
Vertical Stabilisation and Plasma Position and
Shape Control
  • Stabilisation
  • Increased Voltage Possibility was excluded on
    grounds of coil reliability
  • Passive stabilisation being investigated,
    starting with assessment of forces

10
ELM and RWM Coils
Picture frame Concept
Wall Mounted Option
Port Coil Concept Port plugs to be designed to
allow retro-fit
11
Tritium and Dust
Design Change Requests were submitted regarding
both the measurement and removal of tritium and
dust, and accepted for study DCRs 131 and
106 The importance of these issues was accepted,
and C.Alejaldre, the DDG for Safety and Security
has been charged to coordinate these activities
and propose a workable solution. ITER material
strategy Start ITER with carbon divertor and Be
wall to allow a wide range of scoping
studies Change to a W divertor before the end of
the non-active phase to allow characterisation of
the divertor prior to the active phase Watch This
Space !
12
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13
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