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NSTX. Supported by. Developing the Core Physics Scenarios For Next Step STs. Stefan Gerhardt Friday AM Talk at 2011 APS DPP. Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U ORNL PPPL Princeton U Purdue U SNL

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Nstx

NSTX

Supported by

Developing the Core Physics Scenarios For Next Step STs

Stefan Gerhardt

Friday AM Talk at 2011 APS DPP

Columbia U

CompX

General Atomics

FIU

INL

Johns Hopkins U

LANL

LLNL

Lodestar

MIT

Nova Photonics

New York U

ORNL

PPPL

Princeton U

Purdue U

SNL

Think Tank, Inc.

UC Davis

UC Irvine

UCLA

UCSD

U Colorado

U Illinois

U Maryland

U Rochester

U Washington

U Wisconsin

Culham Sci Ctr

U St. Andrews

York U

Chubu U

Fukui U

Hiroshima U

Hyogo U

Kyoto U

Kyushu U

Kyushu Tokai U

NIFS

Niigata U

U Tokyo

JAEA

Hebrew U

Ioffe Inst

RRC Kurchatov Inst

TRINITI

NFRI

KAIST

POSTECH

ASIPP

ENEA, Frascati

CEA, Cadarache

IPP, Jülich

IPP, Garching

ASCR, Czech Rep


Outline of talk 20 slides

Outline of Talk (20 slides)

  • Intro (4 slides)

    • Describe why STs are (potentially) useful. (1 slide)

    • The NSTX facility. (1 slide)

      • Emphasize upgrades in the past 3-4 years that contribute to “advanced” plasmas (routine RMW control, Lithium, improved control).

    • What is the present “best” performance in NSTX. (2 slides)

      • Database analysis of operating space, example discharges.

  • Describe results in three interacting areas (10 slides):

    • Transport (2 slides)

      • Lowest order scanlings….effect of Li?

    • Current drive (4 slides)

      • Cases that are approximately classical without *AE activity.

      • Phenomenological modeling of current redistribution with TAE Avalanches.

      • Achieved non-inductive fractions in NSTX

    • Stability (4 slides)

      • Importance of elevated qmin>1 to avoid core kink/tearing

      • Strong shaping, broad profiles.

      • RWM control

  • NSTX-Upgrade Simulations (4 slides)

    • Describe the methods (1 slide)

    • Example profiles for 100% non-inductive cases w/ Pinj=12.6 MW, BT=1.0T, including thermal profile and confinement scaling sensitivity. (1 slide)

    • Compare a broad range of upgrade scenarios to existing NSTX parameters (2 slides)

      • Separate 100% non-inducive and high-current partial inductive.

      • Emphasize what is similar (bN, H), and what is better (lower collisionality, elevated qmin)

  • 2 Themes:

  • How facility improvements help with scenarios

  • How physics results support the modeling.


How recent facility improvements interact to improve performance

How Recent Facility Improvements Interact to Improve Performance

Eliminate ELMs

Broaden the Conductivity Profile

Reduced PCS Latency

Increase k

Elevate qmin

Avoid core n=1 modes

Lower li

Lithium Conditioning of PFCs

Increase Bootstrap Current

Increase Non-Inductive Fraction

Improved Electron Confinement

n=1 Control

RWM & DEFC

Increase NBCD

Reduce bN Limit

Maintain Rotation

Increase Projected Fusion Gain

Maintain or Increase bN

Eliminate Rapidly Growing RWMs


What is needed

What is needed.

  • Most of the data is well analyzed.

  • Could use:

    • Finish upgrade modeling (SPG work).

    • Conclusion on the Li vs. no-Li confinement trends. Does collisionality explain everything? Pedestal vs. Core?

    • NSTX-U modeling assumes that ion transport remains neoclassical. Do we expect this to be true? GTS calculations started?

    • Elongation scaling of the no-wall limit in NSTX/NSTX-U relevant plasmas.

    • Conditions for TAE Avalanche onset in H-mode plasmas.

    • Is it necessary to say anything about disruptions…their frequency or predictability?


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