PROGRAM PERFORMANCE TARGETS

FY 2011 Annual Performance Targets

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 CMod, NSTX) leading toward the predictive capability for burning plasmas and configuration optimization. FY11: Improve the understanding of the physics mechanisms responsible for the structure of the pedestal and compare with the predictive models described in the companion theory milestone. Perform experiments to test theoretical physics models in the pedestal region on multiple devices over a broad range of plasma parameters (e.g., collisionality, beta, and aspect ratio). Detailed measurements of the height and width of the pedestal will be performed, augmented by measurements of the radial electric field. The evolution of these parameters during the discharge will be studied. Initial measurements of the turbulence in the pedestal region will also be performed to improve understanding of the relationship between edge turbulent transport and pedestal structure.

2.  Continue to 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. FY11: A focused analytic theory and computational effort, including large-scale simulations, will be used to identify and quantify relevant physics mechanisms controlling the structure of the pedestal. The performance of future burning plasmas is strongly correlated with the pressure at the top of the edge transport barrier (or pedestal height). Predicting the pedestal height has proved challenging due to a wide and overlapping range of relevant spatiotemporal scales, geometrical complexity, and a variety of potentially important physics mechanisms. Predictive models will be developed and key features of each model will be tested against observations, to clarify the relative importance of various physics mechanisms, and to make progress in developing a validated physics model for the pedestal height.

3. Average achieved operational time of major national fusion facilities as a percentage of total planned operational time of greater than 90%. FY11: 90% of scheduled operating time.

4.  Cost-weighted mean percent variance from established cost and schedule baselines for the NSTX Upgrades MIE kept to less than 10%. FY11: cost and schedule variance are both less than 10%.

American Recovery and Reinvestment Act Reporting

FY 2010 Annual Performance Targets

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 major fusion facilities to improve understanding of the heat transport in the tokamak scrape- off layer (SOL) plasma, strengthening the basis for projecting divertor conditions in ITER. The divertor heat flux profiles and plasma characteristics in the tokamak SOL will be measured in multiple devices to investigate the underlying thermal transport processes. The unique characteristics of C-Mod, DIII-D, and NSTX will enable collection of data over a broad range of SOL and divertor parameters (e.g., collisionality, beta, parallel heat flux, and divertor geometry). Coordinated experiments using common analysis methods will generate data that will be compared with theory and simulation.

2.  Optimizing confinement and predicting the behavior of burning plasmas require improved simulations of toroidal momentum transport, since it influences plasma rotation which plays a critical role in reducing the loss of heat from the plasma and in stabilizing macroscopic instabilities.

In FY 2010, gyrokinetic simulations of turbulent transport of toroidal momentum with Boltzmann and with kinetic electrons will be carried out. These simulations will explore the Ion Temperature Gradient (ITG) and the Collisionless Trapped Electron Mode (CTEM) regimes.

3. Average achieved operation time of the major national fusion facilities (DIII-D, Alcator C-Mod, NSTX) as a percentage of the total planned operation time in FY10 of greater than 90%.

FY 2009 Annual Performance Targets

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 2009, FES will identify the fundamental processes governing particle balance by systematically investigating a combination of divertor geometries, particle exhaust capabilities, and wall materials. Alcator C-Mod operates with high-Z metal walls, NSTX is pursuing the use of lithium surfaces in the divertor, and DIII-D continues operating with all graphite walls. Edge diagnostics measuring the heat and particle flux to walls and divertor surfaces, coupled with plasma profile data and material surface analysis, will provide input for validating simulation codes. The results achieved will be used to improve extrapolations to planned ITER operation.

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 2009, gyrokinetic edge electrostatic turbulence simulations will be carried out across the divertor separatrix with enhanced resolution down to the ion gyroradius scale.

3. Average achieved operation time of the major national fusion facilities (DIII-D, Alcator C-Mod, NSTX) as a percentage of the total planned operation time in FY09 of greater than 90%.

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.

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.

3.    Average achieved operation time of the major national fusion facilities as a percentage of the total planned operation time in FY 2008 - >90%.

4.    Cost-weighted mean percent variance from established cost and schedule baselines for major construction, upgrade, or equipment procurement projects in FY 2008 - <10%.

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

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

3.    Average achieved operation time of the major national fusion facilities as a percentage of the total planned operation time in FY 2007 - >90%.

4.    Cost-weighted mean percent variance from established cost and schedule baselines for major construction, upgrade, or equipment procurement projects in FY 2007 - <10%.

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

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

3.    Average achieved operation time of the major national fusion facilities as a percentage of the total planned operation time in FY 2006 - >90%.

4.    Cost-weighted mean percent variance from established cost and schedule baselines for major construction, upgrade, or equipment procurement projects in FY 2006 - <10%.

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.

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

3.    Average achieved operation time of the major national fusion facilities as a percentage of the total planned operation time.  FY 2005 - >90%.

4.    Cost-weighted mean percent variance from established cost and schedule baselines for major construction, upgrade, or equipment procurement projects.  FY 2005 - <10%.

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

•  DIII-D    

•  C-Mod

•  NSTX

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

• NCSX

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