Stellarator Program Update: Status of NCSX & QPS

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Presentation transcript:

Stellarator Program Update: Status of NCSX & QPS Hutch Neilson, PPPL for the U.S. Stellarator Community ARIES Project Meeting Lawrence Livermore National Laboratory May 7, 2003 1

Compact Stellarators Are Advancing U.S. Program Goals Provide needed solutions for practical MFE systems. Steady state with no recirculating power for current or rotation drive. Passively stable without active feedback; no disruptions. Low aspect ratio (≤ 4.4) and high beta (≥4%)  high power density. 10-Yr. Goal: Determine attractiveness of compact stellarator. Advance 3D plasma physics understanding important to MFE science generally. Stellarator physics benefits derive from their 3D geometry. More design freedom lets us design for desired plasma properties. Cost: more complex coil geometry. Research: test and understand physics, quantify benefits vs costs, assess overall merit. CS Plasma and Coils

Stellarators Are Making Impressive Progress Large Helical Device (PE w/ S/C magnets - Japan) > 3%. Te ≈ 10 kev, Ti ≈ 5 keV. enhanced confinement. 2-minute pulses. Wendelstein 7-AS (PoP- Germany) > 3%. enhanced confinement. density control & enhanced performance w/island divertor. Recent MHD stability results have favorable implications. – M. Zarnstorff talk. Helically Symmetric Experiment (CE- U. Wisc.) Successful test of quasi-symmetry. New stellarators are coming! NCSX, QPS (2007); W7-X (2009)

Stellarator Proof of Principle Program - 1 Goal is to develop the knowledge base needed to assess compact stellarator attractiveness and decide on next steps. National program consists of several elements, integrating theory, experiment, and design. NCSX PoP Experiment R = 1.4 m, B = 1.2-2.0 T, P = 6 MW (NB) + 6 MW (RF) Based on stable QA plasma with R/a = 4.4,  = 4%. Flexible coils can test high  (up to ≥ 6%), and physics issues: beta limits and limiting mechanisms confinement and flows with quasi-axisymmetry transport reduction NTM stabilization Alfvén mode stability divertor-core compatibility What are the conditions for high-beta, disruption-free operation with no feedback stabilization, current drive, rotation drive, or profile control? NCSX (PPPL-ORNL)

Stellarator Proof-of-Principle Program - 2 HSX (Univ. of Wisconsin) Helically Symmetric Experiment (HSX) Quasi-helical symmetry. Physics diagnostics coming on line. PoP Program Elements (cont’d.) QPS Compact Stellarator CE Exp’t. Quasi-poloidal symmetry at very low R/a. CTH (Auburn U.) Compact Toroidal Hybrid (CTH) 3D equilibrium reconstruction, stability. Under construction- complete late 2003. Stellarator Physics via Theory and International Collaboration. CS Reactor Design Studies (ARIES) Reactor optimization, design for adequate alpha confinement, issue identification.

NCSX Fabrication Project Has Started Industry performing manufacturing R&D for critical components Vacuum Vessel (Forming, Welding, Port Attachment) Modular Coil Winding Form (Casting and Machining) Processes will be developed and demonstrated via prototypes.

Coil Winding Methods Are Being Developed NCSX Winding Cross Section Cast winding forms for epoxy impregnation trials. Test of vacuum impregnation method on straight section. Scale 50 µm Good epoxy penetration into stranded copper conductor.

NCSX Plans for Next 2 Years: Fabricate Major Stellarator Components, Start Assembly Fabricate Vacuum Vessel Fabricate Modular Coil Winding Forms Assemble Field Periods Wind Coils 2

QPS Will Extend Physics Understanding to Very Low R/a and Quasi-Poloidal Symmetry Focus on stellarator confinement improvement at very low R/a confinement scaling flux surface robustness reduction of neoclassical transport reduction of anomalous transport correlation of fluctuations with transport Rpl = 0.9-1 m, apl = 0.3-0.4 m Vpl = 2-3 m3, Aspect ratio > 2.3 B = 1 ± 0.2 T (1.5 s), PRF = 2-4 MW

QPS Configuration Has Considerable Flexibility Neoclassical transport losses can be changed by factor ~20-80 Varying coil currents allows changing the degree of quasi-poloidal symmetry and poloidal flow damping over a wide range Vacuum magnetic configuration close to full- beta configuration

Project Status and Plans NCSX Fabrication project started April 1. Preliminary Design Review planned for September in preparation for establishing project baseline. Major component manufacture starts in early 2004. First plasma in 2007 QPS Physics Validation Review completed, Mission Need approved. Conceptual Design Review planned for June 24-25, 2003. Complete design and begin modular coil R&D in 2004 in preparation for project start in October, 2005. First plasma in 2007.

Summary Stellarators are advancing U.S. fusion program goals. Practical MFE configurations. Fundamental physics understanding. Integrated national stellarator program is already making excellent progress. Physics understanding from HSX, theory, collaborations. New experiments moving from plans to reality. First steps in compact stellarator reactor explorations.