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ANNUAL PROGRAM PERFORMANCE TARGETS
FY 2008
Goal:
Answer the key
scientific questions and overcome enormous
technical challenges to harness the power that
fuels a star, realizing by the middle of this
century a landmark scientific achievement by
bringing "fusion power to the grid."
1.
Conduct experiments on the major fusion
facilities (DIII-D, Alcator C-Mod, NSTX) leading
toward the predictive capability for burning
plasmas and configuration optimization. In
FY 2008, FES will evaluate the generation of
plasma rotation and momentum transport, and
assess the impact of plasma rotation on
stability and confinement. Alcator-Mod
will investigate rotation without external
momentum input, NSTX will examine very high
rotation speeds, and DIII-D will vary rotation
speeds with neutral beams. The results
achieved at the major facilities will provide
important new data for estimating the magnitude
of and assessing the impact of rotation on ITER
plasmas.
|
Quarter |
Statement of Quarterly Target |
Link to Report
(to be activated when available) |
|
First |
Develop a
research plan and prepare the three
facilities as necessary to accomplish the
required experiments. |
X |
|
Second |
Begin conducting
planned experiments on at least one of the
three facilities. |
X |
|
Third |
With experiments
and analysis in progress at multiple
facilities, make an initial evaluation of
the results to date, and adjust plans as
necessary. |
X |
|
Fourth |
Complete the
required experiments and prepare a joint
report summarizing the data and analysis
contributing to estimating the magnitude,
and assessing the impact, of rotation on
ITER. |
X |
2.
Increase resolution in simulations of plasma
phenomena -- optimizing confinement and
predicting the behavior of burning plasmas
require improved simulations of edge and core
plasma phenomena, as the characteristics of the
edge can strongly affect core confinement.
|
Quarter |
Statement of Quarterly Target |
Link to Report
(to be activated when available) |
|
First |
Finish
parallelization and testing of the newest
TORIC-LH solver that directly couples the
slow wave polarization of the lower hybrid (LH)
wave. |
X |
|
Second |
Validate an
Alcator C-Mod LH simulation with TORIC-LH on
the CRAY XT3/XT4 Jaguar facility at ORNL
using 1000 radial elements and 1023 poloidal
modes. |
X |
|
Third |
Test scaling of
the TORIC-LH solver for resolutions greater
than 1023 poloidal modes with the number of
radial elements fixed at 1000 for the
Alcator C-Mod test case. |
X |
|
Fourth |
Complete the
2047 poloidal mode target case for Alcator
C-Mod using 1000 radial elements on the CRAY
XT3/XT4 Jaguar facility. |
X |
3. Average achieved operation time of the major
national fusion facilities as a percentage of the
total planned operation time in FY 2008 - >90%.
|
Statement of Target Accomplishment |
Daily Operations Logs |
|
Projected to Meet Goal |
DIII-D |
|
Projected to Meet Goal |
C-Mod |
|
Projected to Meet Goal |
NSTX |
4. Cost-weighted mean percent variance from
established cost and schedule baselines for major
construction, upgrade, or equipment procurement
projects in FY 2008 - <10%.
|
Statement of Target Accomplishment |
Project Director's Monthly Report |
|
Projected to Meet Goal |
NCSX |
FY 2007
Goal: Answer the key
scientific questions and overcome enormous
technical challenges to harness the power that
fuels a star, realizing by the middle of this
century a landmark scientific achievement by
bringing "fusion power to the grid."
1.
Conduct experiments on the major fusion facilities
(DIII-D, Alcator C-Mod, NSTX) leading toward the
predictive capability for burning plasma and
configuration optimization. In FY 2007 FES
will measure and identify magnetic modes on NSTX
that are driven by energetic ions traveling
faster than the speed of magnetic perturbations
(Alfvén
speed); such modes as ITER.
Complete Milestone Report
|
Quarter |
Statement of Quarterly Target |
Link to Report
|
|
First |
At the NSTX Research Forum,
complete development of a plan for the NSTX
research campaign to study magnetic modes
driven by energetic particles. (Dec 31, 2006) |
X |
|
Second |
Commission and calibrate
diagnostics tools and data acquisition
hardware on the NSTX device. (March 31,
2007) |
X |
|
Third |
Measure
supra-Alfvénic
fast ion driven magnetic modes, covering
frequencies up to a substantial fraction of
the deuterium ion gyrofrequency. (June 30, 2007) |
X |
|
Fourth |
Identify
magnetic modes and mode behaviors associated
with the super-Alfvénic
fast ions and compare with modes associated
with sub-Alfvénic
fast ions published in the literature. (September 30, 2007) |
X |
2. Increase resolution in
simulations of plasma phenomena--optimizing
confinement and predicting the behavior of
burning plasmas require improved simulations of
edge and core plasma phenomena, as the
characteristics of the edge can strongly affect
core confinement. In FY 2007, improve the
simulation resolution of linear stability
properties of Toroidal Alfvén
Eigenmodes driven by energetic particles and
neutral beams in ITER by increasing the number
of toroidal modes used to 15.
Milestone Reports
|
Quarter
|
Statement of Quarterly Target |
Link to Report
|
|
First |
Develop
fiducial ITER numerical equilibria, using
the simulation code TRANSP, to determine the
alpha-particle slowing down distribution and
neutral beam ions for a range of operating
regimes. (Dec 31, 2006) |
X |
|
Second |
Analyze the normal shear discharges,
performing a parameter scan to determine the
linear stability of toroidal mode number n =
1-15 TAE modes. (March 31, 2007) |
X |
|
Third |
Analyze the hybrid shear discharges,
performing a parameter scan to determine the
linear stability o toroidal mode number n -
1-15 TAE modes. (June 30,
2007) |
X |
|
Fourth |
Analyze the reversed shear discharges,
performing a parameter scan to determine the
linear stability of toroidal mode number n -
1-15 TAE modes, and prepare a comprehensive
review of the TAE stability of ITER
discharges in the three operating regimes. (September
30, 2007) |
X |
3. Average achieved operation time of the major
national fusion facilities as a percentage of the
total planned operation time in FY 2007 - >90%.
|
Statement of Target Accomplishment |
Daily Operations Logs |
|
Projected to Meet Goal |
DIII-D |
|
Projected to Meet Goal |
C-Mod |
|
Projected to Meet Goal |
NSTX |
4. Cost-weighted mean percent variance from
established cost and schedule baselines for major
construction, upgrade, or equipment procurement
projects in FY 2007 - <10%.
|
Statement of Target Accomplishment |
Project Director's Monthly Report |
|
Projected to Meet Goal |
NCSX |
FY 2006
Goal: Answer the key
scientific questions and overcome enormous
technical challenges to harness the power that
fuels a star, realizing by the middle of this
century a landmark scientific achievement by
bringing "fusion power to the grid."
1.
Conduct experiments on the major fusion facilities
(DIII-D, Alcator C-Mod, NSTX) leading toward the
predictive capability for burning plasma and
configuration optimization. In FY 2006 FES will
inject 2 MW of neutral power in the counter
direction on DIII-D and will begin physics
experiments.
Complete Milestone Report
|
Quarter |
Statement of Quarterly Target |
Link to Report |
|
First |
Install new
beamline port with modifications needed for
counter injection. (Dec 31, 2005) |
X |
|
Second |
Complete
installation of the new beamline hardware (beamline
support strands, and spools). (March 31,
2006) |
X |
|
Third |
Complete
beamline hardware system checkout. Install
refurbished ion sources and ready new beam
system for operation. (June 30, 2006) |
X |
|
Fourth |
Inject 2 MW of
deuterium neutrals into plasma from new
beamline. Measure impact on rotation.
Document results. (September 30, 2006) |
X |
2. Increase resolution in simulations of plasma
phenomena--optimizing confinement and predicting
the behavior of burning plasmas require improved
simulations of edge and core plasma phenomena, as
the characteristics of the edge can strongly
affect core confinement. In FY 2006 FES will
simulate nonlinear plasma edge phenomena using
extended MHD codes with a resolution of 40
toroidal modes.
Milestone Reports
|
Quarter
|
Statement of Quarterly Target |
Link to Report
|
|
First |
Run simplified, nonlinear, time-dependent
computations with realistic initial edge
conditions to find plasma conditions for use
in full nonlinear studies of edge
instabilities. (Dec 31, 2004) |
X |
|
Second |
Perform extended, linear perturbation studies
to investigate the role of plasma edge density
gradients. The representation of the vessel
wall will be improved to more accurately
represent the DIII-D wall. (March 31, 2005) |
X |
|
Third |
Incorporate refinements to the plasma
conditions and improved accuracy of the DIII-D
geometry and profiles into full nonlinear
studies of edge instabilities. (June 30,
2005) |
X |
|
Fourth |
Nonlinear plasma edge phenomena will be
simulated using extended MHD codes with a
resolution of 40 toroidal modes. (September
30, 2005) |
X |
3. Average achieved operation time of the major
national fusion facilities as a percentage of the
total planned operation time in FY 2006 - >90%.
|
Statement of Target Accomplishment |
Daily Operations Logs |
|
Projected to Meet Goal |
DIII-D |
|
Projected to Meet Goal |
C-Mod |
|
Projected to Meet Goal |
NSTX |
4. Cost-weighted mean percent variance from
established cost and schedule baselines for major
construction, upgrade, or equipment procurement
projects in FY 2006 - <10%.
|
Statement of Target Accomplishment |
Project Director's Monthly Report |
|
Projected to Meet Goal |
NCSX |
FY
2005
Goal: Answer the key
scientific questions and overcome enormous
technical challenges to harness the power that
fuels a star, realizing by the middle of this
century a landmark scientific achievement by
bringing "fusion power to the grid."
1. Conduct experiments on the major fusion
facilities (DIII-D, Alcator C-Mod, NSTX) leading
toward the predictive capability for burning
plasma and configuration optimization. In FY 2005
FES will measure plasma behavior in Alcator C-Mod
with high-Z antenna guards and input power greater
than 3.5 MW.
|
Quarter
|
Statement of Quarterly Target |
Link to Report
|
|
First |
Install molybdenum protection tiles on all RF
antennas and remove boron-nitride tiles from
active MHD antennas. (Dec 31, 2004) |
X |
|
Second |
Begin measurements of plasma behavior with all
high-Z antenna guards during tokamak
operation. (March 31, 2005) |
X |
|
Third |
Assess operation with significant auxiliary
input power for L-Mode and H-Mode plasma
regimes. (June 30, 2005) |
X |
|
Fourth |
Operate with input power in excess of 3.5 MW,
measure plasma behavior, compare with previous
operation using boron-nitride protection
tiles; document results in a Target Completion
Report. (September 30, 2005) |
X |
2. Increase resolution in simulations of plasma
phenomena--optimizing confinement and predicting
the behavior of burning plasmas require improved
simulations of edge and core plasma phenomena, as
the characteristics of the edge can strongly
affect core confinement. In FY 2005 FES will
simulate nonlinear plasma edge phenomena using
extended MHD codes with a resolution of 20
toroidal modes.
Milestone Reports
|
Quarter
|
Statement of Quarterly Target |
Link to Report
|
|
First |
Quantify the scaling of unstable modes with
resistively and thermal conduction, and
compare to linear code. (Dec 31, 2004) |
X |
|
Second |
Do simulations using accurate experimental
profiles, and extend models to include ion
stress tensor effects. (March 31, 2005) |
X |
|
Third |
Further extend the studies to include
variation of the electron pressure along field
line, and look for appropriate equilibrium for
test cases. (June 30, 2005) |
X |
|
Fourth |
Run simulations with up to 20 modes including
density evolution, and extend deep into the
nonlinear regime; document results in a Target
Completion Report. (September 30, 2005) |
X |
3. Average achieved operation time of the major
national fusion facilities as a percentage of the
total planned operation time. FY 2005 - >90%.
|
Statement of Target Accomplishment |
Daily Operations Logs |
|
Met Goal |
DIII-D |
|
Met Goal |
C-Mod |
|
Met Goal |
NSTX |
4. Cost-weighted mean percent variance from
established cost and schedule baselines for major
construction, upgrade, or equipment procurement
projects. FY 2005 - <10%.
|
Statement of Target Accomplishment |
Project Director's Monthly Report |
|
Met Goal |
NCSX |
FY
2004
1. "Average achieved operation time of the
major national fusion facilities as a percentage
of the total planned operation time is greater
than 90%." For Fusion Energy Sciences in FY
2004: DIII-D, C-Mod, NSTX
Met
Goal
2. "Cost-weighted mean percent variance from
established cost and schedule baselines for major
construction, upgrade, or equipment procurement
projects is kept to less than 10%." For Fusion
Energy Sciences in FY 2004: National Compact
Stellarator Experiment (NCSX)
Met
Goal
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