Plasma Chamber

1
Plasma Chamber
Prepared byM. Abdou, A. Ying, N. Morley, C.
Wong, D. Sze, M. Sawan,P. Calderoni, S. Malang,
M. Dagher, S. Smolentsev (on behalf of the
Plasma Chamber Community)
VLT Meeting, Washington DC, August 25, 2005
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Key RD Thrusts over the next 5 years for the VLT
Area

• MHD Thermofluid Modeling and Experiments
• Solid Breeder Thermomechanics and Tritium
  Recovery
• Tritium Control and Predictive Capability
• 4. VTBM Virtual TBM (Integrated Modeling)
• Design and Analysis of TBM Test Articles and
  Ancillary Equipment
• Sub-Component Verification Tests
• Mockup Facilities Design, Construction and
  Operation
• Diagnostics / Instrumentation / Control
• TBWG International Testing Program and ITER/
  Parties Interface
• Tritium Supply and Self-Sufficiency

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Descriptions of RD thrusts

• 1. MHD Thermofluids Modeling and
  ExperimentsExperiments and modeling in 3-D
  complex geometry and multi-component magnetic
  fields and gradients. Explore fluid flow
  behavior, heat, and mass transfer of flow channel
  inserts (as thermal and electrical insulators) in
  liquid metal flows, and effects of LM exposure
  and temperature gradients on long-term FCI
  performance. Characterize flow behavior in
  external elements such as feed pipes and
  manifolds, and investigate natural convection in
  volumetrically heated channels.
• 2. Solid Breeder Thermomechanics and Tritium
  RecoveryExperiments and modeling on the effect
  of stress-induced time-dependent strain
  deformation on blanket thermal and tritium
  release performance. Investigate limits
  (temperature window) of tritium release.
• 3. Tritium Control and Predictive
  CapabilityExplore methods, conduct experiments
  and develop models to predict and control tritium
  transport in fusion systems, accounting for
  convective, isotope swamping, and geometric
  effects under relevant pressure and temperature
  regimes.

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Descriptions of RD thrusts (contd)

• 4. VTBM Virtual TBM (Integrated
  Modeling)Develop numerical simulation tools and
  common data structure for overall system
  simulation of TBM performance and operation,
  coupling various advanced simulation tools for
  nuclear heating, thermofluid MHD, structural
  mechanics, corrosion and solute transport, etc.
  Will be used to predict steady-state and
  transient TBM behavior in ITER. The VTBM will be
  used to guide designs of TBM and mockups, as well
  as predict and interpret results from
  sub-component and mockup tests. Results from
  testing in ITER will be used to validate the VTBM
  for use in design and analysis of blankets for
  future systems, DEMO, and power plants.
• 5. Design and Analysis of TBM Test Articles and
  Ancillary EquipmentComplete conceptual design,
  carry out preliminary and final design and
  analysis of TBM test articles and associated
  ancillary equipment (piping, heat exchangers,
  tritium processing, pumps, etc.).
• 6. Sub-Component Verification TestsTests for
  specific elements of TBM article design to verify
  computational predictions (or obtain direct
  experimental data) and performance projections of
  sub-components, particularly in areas where there
  are large uncertainties in data or methods (e.g.,
  flow distribution in complex manifolds, co-axial
  piping performance)
• 7. Mockup Facilities Design, Construction and
  OperationInvestigate facilities required for
  scaled mockup (e.g., ¼, ½ size) tests of TBM (use
  or upgrade existing facilities or design and
  construct new ones) with key environmental
  conditions to simulate the ITER environment.
  Design and test mockups for validation and
  qualification of performance, fabrication
  methods, etc.

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Descriptions of RD thrusts (contd)

• 8. Diagnostics / Instrumentation /
  ControlIdentify suitable diagnostic and
  measurement systems that can operate in the
  nuclear/electromagnetic environment of ITER,
  taking into consideration the chemical systems of
  the TBM, including PbLi compatibility,
  high-pressure helium, activated materials, etc.
  Corresponding operational control systems will
  also be considered.
• 9. TBWG International Testing Program and
  ITER/Parties InterfacePerform tasks as required
  by the ITER International Testing Program
  responsible for the interface with the ITER basic
  device, developing qualification requirements and
  acceptance criteria, and coordination of tests
  among the ITER Parties. Also, Bi-lateral and
  multi-lateral international collaborative RD for
  TBM.
• 10. Tritium Supply and Self-SufficiencyDynamic
  simulation of world tritium supply and
  consumption and assessment of the tritium supply
  issue. Evaluate the need for and practicality of
  outboard breeding blanket in ITER second phase.
  Develop comprehensive fuel cycle dynamics model
  to predict tritium behavior, transport, and
  inventories in all system components such as
  plasma exhaust, PFC, blankets, and tritium
  processing. Determine phase space of plasma,
  nuclear, material and technological conditions in
  which self-sufficiency can be attained.

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Current Spending on Plasma Chamber Thrusts

• Thrusts 1, 2, 3, 5, 9, 10
• 1225 K
• Thrusts 4, 6, 7, 8
• 0 K
• Notes
• There is 731 K from PFC for MHD thermofluid
  modeling and experiments that are dual use for
  PFC and Plasma Chamber
• There is 560 K from JUPITER-II that are dual
  use with Plasma Chamber
• The cost of operating facilities is shared among
  various programs and activities

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Characterization of RD thrusts to VLT missions
Supports providing T-breeding capabilities in
ITER second phase (years 11-20)