Plasma Chamber
Prepared by
M. Abdou, A. Ying, N. Morley, C. Wong, D. Sze, M. Sawan,
P. Calderoni, S. Malang, M. Dagher, S. Smolentsev, B. Merrill
(on behalf of the Plasma Chamber Community)
VLT Meeting, Washington DC, August 25, 2005
Key R&D Thrusts over the next 5 years for the VLT Area
1.
2.
3.
4.
5.
MHD Thermofluid Modeling and Experiments
Solid Breeder Thermomechanics and Tritium Recovery
Tritium Control and Predictive Capability
VTBM: Virtual TBM (Integrated Modeling)
Design and Analysis of TBM Test Articles and Ancillary
Equipment
6. Sub-Component Verification Tests
7. Mockup Facilities Design, Construction and Operation
8. Diagnostics / Instrumentation / Control
9. “TBWG” International Testing Program and ITER/ Parties
Interface
10. Tritium Supply and Self-Sufficiency
2
Descriptions of R&D thrusts
1.
2.
3.
MHD Thermofluids Modeling and Experiments
Experiments and modeling in 3-D complex geometry and multicomponent 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.
Solid Breeder Thermomechanics and Tritium Recovery
Experiments and modeling on the effect of stress-induced timedependent strain deformation on blanket thermal and tritium release
performance. Investigate limits (“temperature window”) of tritium
release.
Tritium Control and Predictive Capability
Explore 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.
3
Descriptions of R&D thrusts (cont’d)
4.
5.
6.
7.
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.
Design and Analysis of TBM Test Articles and Ancillary Equipment
Complete 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.).
Sub-Component Verification Tests
Tests 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)
Mockup Facilities Design, Construction and Operation
Investigate 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.
4
Descriptions of R&D thrusts (cont’d)
8.
Diagnostics / Instrumentation / Control
Identify 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 Interface
Perform 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 R&D for
TBM.
10.
Tritium Supply and Self-Sufficiency
Dynamic 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.
5
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
6
Characterization of R&D thrusts to VLT missions
Support US
Contribution
to ITER
(Dual Use
Technology)
Additional
R&D to
support
ITER
ITER utilization
as test bed
(TBM, etc.)
Next
generation
technology
(current, future
machines)
X
Longer-term
R&D
(for machines
beyond ITER)
MHD Thermofluids
X
X
SB Thermomechanics & T
Recovery
*
X
X
T Control & Predictive
Capability
X
X
X
*
*
X
X
X
*
*
X
X
X
X
X
X
X
TBWG & ITER Interface
*
X
T Supply & Self-Sufficiency
X
X
Virtual TBM
TBM Design and Analysis
Verification Tests
Mockup Facilities & Tests
Diagnostics
X
X
X
X
X
X
* Supports providing T-breeding capabilities in ITER second phase (years 11-20)
7