Raman,11 STW 3-6 Oct 2005 Fueling Requirements for Steady State Spherical Torus Operation Roger Raman, Thomas R. Jarboe, + Henry W. Kugel University of.

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Presentation transcript:

Raman,11 STW 3-6 Oct 2005 Fueling Requirements for Steady State Spherical Torus Operation Roger Raman, Thomas R. Jarboe, + Henry W. Kugel University of Washington, Seattle + Princeton Plasma Physics Laboratory Joint Meeting of the 3rd IAEA technical Meeting on Spherical Torus and the 11th International Workshop on Spherical Torus 3-6 October 2005, St Petersburg, Russia Work supported by DOE grant No. DE-FG03-02ER54686 Supported by

Raman,11 STW 3-6 Oct 2005 Early Work on CT Injection Perkins (LLNL) and Parks (GA) proposed concept for fueling -[Perkins, Ho, Hammer, NF 28, 1365 (1988) & Parks, Phys. Rev. Lett. 61, 1364 (1988)] Hammer and Hartman (LLNL) developed the accelerator concept -[Hammer and Hartman, Phys. Rev. Lett., 61, 2843 (1988)] First tokamak fueling (CT size < Tok. size) -[Raman et. al,. Phys. Rev. Lett. 73, 3101 (1994)].

Raman,11 STW 3-6 Oct 2005 Outline of Talk –Spherical Torus has high beta and high bootstrap frac. Optimized profiles –Present systems may be inadequate Pellets sizes are large & injection is shallow No plan at present for density profile control Density profile control ideal method for steady burn control –Compact Toroid (CT) injection system has potential for density profile control and momentum injection –Status of current work Open issues Plans and suggestions

Raman,11 STW 3-6 Oct 2005 Flexible fueling system may be the only choice for burn control in steady-state ST discharges A burning plasma device has no need for neutral beam injection for plasma heating and alphas are isotropic → no momentum injection In a device with high bootstrap current fraction, optimized density and pressure profiles must be maintained → fueling system must not adversely perturb established density and pressure profiles Other than a system for current drive, a fueling system is all that a burning plasma system may be able to rely on to alter core plasma conditions and for burn control –Fusion power output scales as the square of density –Initial density peaking via. core fuelling provides more flexibility to reach ignition

Raman,11 STW 3-6 Oct 2005 Fueling profiles from present systems Pellets (< 1km/s, HFS) –Large pellets increases density over a large radius –Capability of small pellets for profile control yet to be established Supersonic gas (~ 2-3 km/s) –Fuels from the edge with improved fueling efficiency –Capability for profile control not known yet Plasma jet (~ 30km/s) –Similar to supersonic gas, bulk fueling at present –Penetration into large cross-section plasmas not known

Raman,11 STW 3-6 Oct 2005 In a CT injection system a CT is accelerated to high velocity and injected into the target plasma to achieve deep fueling CT Penetration time: few µs CT Dissociation time: < 100 µs Density Equilibration time: µs Variable Penetration depth: edge to beyond the core

Raman,11 STW 3-6 Oct 2005 CTs formed in a magnetized Marshall gun on fast (~10 µs) time scales

Raman,11 STW 3-6 Oct 2005 A CT Fueller forms and accelerates CTs in a coaxial rail gun in which the CT forms the sliding armature Amount of gas injected controls CT density Applied voltage controls CT velocity Control system specifies fuel deposition location for each pulse Raman et al., Fusion Techn., 24, 239 (1993)

Raman,11 STW 3-6 Oct 2005 Status of current work TdeV tokamak discharges beneficially fueled by CTs, without causing any adverse perturbation TdeV R = 0.86m a = 0.25m B T = 1.4T Ip = 160kA

Raman,11 STW 3-6 Oct 2005 JFT-2M results (IAEA 2002) K.Tsuzuki et al., EX-C1-1, Proc. IAEA 2002, Lyon, France

Raman,11 STW 3-6 Oct 2005 Conceptual study of a CT system for ITER yields an attractive design R. Raman and P. Gierszewski, ITER Task D315 (1997), Fusion Engin. & Design (1998) <1% particle inventory perturbation, 20 Hz operation

Raman,11 STW 3-6 Oct 2005 ITER CT Injector parameters CT radius0.1 m CT length0.2 m CT density (D + T) 9 x m -3 CT mass2.2 mg DT (2.6 T 2 ) Fueling rate (D + T)5.3 x / pulse Fueling frequency≤ 20 Hz CT velocity300 km/s CT kinetic energy100 kJ (120 kJ T2) Momentum inj. rate13.2 kg.m/s DT, 15.6 T 2, Power consumption8 MWe (10 T 2 ) (Raman and Gierszewski, Fusion Engin. Design (1998) 977 & ITER Task D315)

Raman,11 STW 3-6 Oct 2005 Previous experiments too small to study localized core fueling Approximate relative sizes of various target plasmas and CTs. A CTF sized CT will do far more localized fueling on a NSTX sized device - Steep B T more precisely determines CT stopping location Ref: R. Raman and K. Itami, Journal of Plasma and Fusion Research, (2000) Open Issues

Raman,11 STW 3-6 Oct 2005 Proposed research Plan Injection into a large cross-section, low field device (eg., NSTX) - using an existing injector –Establish localized fueling (~ 2 yr) - Transport studies –Establish momentum injection (~ 2 +1 yrs) –Establish multi-pulse fueling (~3 + 1 yrs) Intermediate scale experiments (JT-60U,JET) –Conduct burning plasma injector design –Re: design study for JT60U (R. Raman and K. Itami, Journal of Plasma and Fusion Research, (2000))

Raman,11 STW 3-6 Oct 2005 The CTF-II injector (in storage at PPPL)

Raman,11 STW 3-6 Oct 2005 The CT Formation bank power supply (110V AC input)

Raman,11 STW 3-6 Oct 2005 A CT injector could provide profile control capability CTPellet Particle invent. perturbation for deep fueling Few % - will not destroy optimized profiles, allows precision fueling capability to adjust profiles Typically 50% on DIII-D - large pellets needed to deposit small fraction of fuel in core Optimal injector location Outboard mid-plane - tangential injection will impart momentum ‘True’-Inboard mid-plane - injection at an angle reduces penetration Real time density feedback control capability Yes - potential for fuel deposition location specification on each pulse using control system request - Also a source of momentum injection Improbable because large pellets fuel entire discharge and mechanical nature of injector reduces fueling flexibility

Raman,11 STW 3-6 Oct 2005 The ability to inject CTs significantly expands NSTX experimental capability Precise H-mode initiation capability valuable for on-going XPs Electron Transport Barrier studies Transport studies by isotopic impurity tailoring Reconnection studies Momentum injection studies for transport barrier sustainment Precise density profile control needed for NSTX SS discharges Local current injection to suppress NTMs ?

Raman,11 STW 3-6 Oct 2005 Conclusions A CT injector has the potential to deposit fuel in a controlled manner at any point in the machine In a Steady State ST device with only RF for current drive, a flexible fueling system may be the only internal profile control tool –Inject momentum for plasma beta and stability –Precise density profile control to optimize bootstrap current and to maintain optimized fusion burn conditions –Study core transport in present machines (He ash removal studies, ELM control) Large STs should consider and develop backup options to meet the fuelling requirements of future devices –Large STs are an attractive target for developing CT fueling -Steep B T gradient, large crossection Essential CT data needed for an ITER CT injector design could be obtained on NSTX using an existing injector

Raman,11 STW 3-6 Oct 2005 No evidence for metallic impurity contamination of TdeV

Raman,11 STW 3-6 Oct 2005 Edge fueling of diverted discharges triggers improved confinement behavior

Raman,11 STW 3-6 Oct 2005 Inductive quality discharge produced by electrode discharge Raman, et al., NF 45 (2005) L15-L19

Raman,11 STW 3-6 Oct 2005 CT induced confinement improvement also seen on STOR-M* * Recent similar results on JFT-2M STOR-M R = 0.46 m A = 0.12 m Ip = 20 kA B T = 1T C. Xiao, A. Hirose, R. Raman, 2001, Compact Torus Injection Experiments in the STOR-M Tokamak, Proc. of 4th Symp. on Current Trends in International Fusion Research: Review and Assessment (Washington D.C., March 12-16, 2001, in print)