Physics Issues and Trade-offs in Magnetic Fusion Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA APS April 2002 Meeting.

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EVOLUTION OF VISIONS FOR TOKAMAK FUSION POWER PLANTS

Historical Perspectives and Pathways to an Attractive Power Plant

Farrokh Najmabadi Professor of Electrical & Computer Engineering

Advanced Design Activities in US

New Development in Plasma and Coil Configurations

Presentation transcript:

Physics Issues and Trade-offs in Magnetic Fusion Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA APS April 2002 Meeting April 20-23, 2002 Albuquerque, NM You can download a copy of the paper and the presentation from the ARIES Web Site: ARIES Web Site:

ARIES Program What is possible What is important Theory Program Stimulus for new ideas Models & concepts Experiments What to demonstrate What has been achieved Progress in Plasma Physics: Macroscopic stability; Wave-particle interaction; Microturbulence & transport Plasma-material Interaction Progress in Other Fusion Sciences … Analysis of Conceptual Fusion Power Plants Identifies Key R&D Issues and Provides a Vision for Fusion Research  Trade-off among disciplines and systems usually determine: The optimum regime of operation; The most useful dimensionless parameters; most effective experiments for the moment; The most cost-effective routes to the evolution of the experimental, scientific and technological program.

Trade-offs Among Systems Determine Optimum Regimes of Operation MHD Figure of Merit BT2BT2  = a/R=1/A Almost Constant for B T fixed at the TF coil  For Superconducting Tokamaks, it is  (i.e.,  R/a) that is important, not  Fusion power density, P f ~  2 B T 4 = (    B T 2 ) 2 Other Examples  Trade-off between bootstrap current fraction and   Advanced Tokamak Regime  Trade-off between vertical stability and plasma shape  Trade-off between plasma edge condition and plasma facing components capabilities,  …

 p /A (  Bootstrap current fraction)  A/S (  Plasma  PU: Pulsed Operation SS: 2nd Stability FS: 1st Stability, steady-state RS: Reversed-shear Advanced Tokamak Regime Is Based on the Trade-off Between MHD and Bootstrap “Conventional” high-  tokamaks (Pulsed operation) 2nd Stability high-  tokamaks (Too much bootstrap) Advanced tokamak (Balanced bootstrap) Current focus of tokamak research

ARIES-I’Pulsar For the same physics and technology basis, steady-state devices outperform pulsed tokamaks  Physics needs of pulsed and steady-state first stability devices are the same (except non-inductive current-drive physics). Medium (~ 8 m major radius)High (> 9 m major radius)Size and Cost Non-inductive drive Expensive & inefficient PF System Very expensive but efficient Current-drive system HighLowRecirculating Power High Bootstrap, High A, Low I Optimum Plasma Regime Yes, 65-%-75% bootstrap fraction  N ~ 3.3,  No, 30%-40% bootstrap fraction  N ~ 3,  Current profile Control Higher (B ~ 16 T on coil) Lower because of interaction with PF (B ~ 14 T on coil) Toroidal-Field Strength MediumLowPower Density

Increase Power Density Directions for Improvement Decrease Recirculating Power Fraction What we pay for,V FPC r  Power density, 1/V p r >  r ~  r <  Improvement “saturates” at ~5 MW/m 2 peak wall loading (for a 1GWe plant). A steady-state, first stability device with Nb 3 Sn technology has a power density about 1/3 of this goal. Big Win Little Gain Improvement “saturates” about Q ~ 40. A steady-state, first stability device with Nb 3 Sn Tech. has a recirculating fraction about 1/2 of this goal. High-Field Magnets ARIES-I with 19 T at the coil (cryogenic). Advanced SSTR-2 with 21 T at the coil (HTS). High bootstrap, High  2 nd Stability: ARIES-II/IV Reverse-shear: ARIES-RS, ARIES-AT, A-SSRT2

Reverse Shear Plasmas Lead to Attractive Tokamak Power Plants First Stability Regime  Does Not need wall stabilization (Resistive-wall modes)  Limited bootstrap current fraction (< 65%), limited  N = 3.2 and  =2%,  ARIES-I: Optimizes at high A and low I and high magnetic field. H-mode confinement Reverse Shear Regime  Requires wall stabilization (Resistive-wall modes)  Excellent match between bootstrap & equilibrium current profile at high   Internal transport barrier  ARIES-RS (medium extrapolation):  N = 4.8,  =5%, P cd =81 MW (achieves ~5 MW/m 2 peak wall loading.)  ARIES-AT (aggressive extrapolation):  N = 5.4,  =9%, P cd =36 MW (high  is used to reduce peak field at magnet)

Approaching COE insensitive of current drive Approaching COE insensitive of power density Evolution of ARIES Designs 1 st Stability, Nb 3 Sn Tech. ARIES-I’ Major radius (m)8.0   ) 2% (2.9) Peak field (T)16 Avg. Wall Load (MW/m 2 )1.5 Current-driver power (MW)237 Recirculating Power Fraction0.29 Thermal efficiency0.46 Cost of Electricity (c/kWh)10 Reverse Shear Option High-Field Option ARIES-I % (3.0) ARIES-RS 5.5 5% (4.8) ARIES-AT % (5.4)

Our Vision of Magnetic Fusion Power Systems Has Improved Dramatically in the Last Decade, and Is Directly Tied to Advances in Fusion Science & Technology Estimated Cost of Electricity (c/kWh)Major radius (m) Approaching COE insensitive of power density High Thermal Efficiency High  is used to lower magnetic field

ARIES designs Correspond to Experimental Progress in a Burning Plasma Experiment Improved Physics “Conventional” Pulsed plasma: Explore burn physics ARIES-RS (reverse shear): Improvement in  and current-drive power Approaching COE insensitive of current drive Explore reversed-shear plasma a) Higher Q plasmas b) At steady state ARIES-AT (aggressive reverse shear): Approaching COE insensitive of power density High  is used to reduce toroidal field Explore envelopes of steady-state reversed-shear operation Demonstrate steady-state first- stability operation. Pulsar (pulsed-tokamak): Trade-off of  with bootstrap Expensive PF system, under-performing TF ARIES-I (first-stability steady-state): Trade-off of  with bootstrap High-field magnets to compensate for low 

Conclusions  Progress in fusion sciences in the last decade is impressive.  Visions for fusion power systems provide essential guidance to R&D directions of the program. They indicate that fusion can achieve its potential as a safe, clean, and economically attractive power source.  Next-step burning plasma experiment(s) will provide essential plasma physics necessary for fusion power.  A strong base program in parallel with burning plasma experiments is necessary: Smaller experiments focus on high pay-off, high risk issues. Progress in other fusion sciences lag behind plasma physics.