skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Extending the low-recycling, flat temperature profile regime in the lithium tokamak experiment-β (LTX-β) with ohmic and neutral beam heating

Journal Article · · Nuclear Fusion
ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ORCiD logo; ; ORCiD logo; ORCiD logo; ORCiD logo

Recent experiments in the Lithium Tokamak Experiment-β (LTX-β) have extended the duration, performance, operating conditions, and diagnosis of the flat-temperature profile, low-recycling regime first observed in LTX. As expected, Li retains hydrogen and suppresses edge neutral cooling, allowing increased edge electron temperature, roughly equal to the core Te. Flat temperature profiles had been obtained transiently in LTX, as the plasma density decayed following the cessation of edge gas puffing. Careful control over the fueling in LTX-β has now been shown to sustain the flat Te profile and hot edge unique to the low-recycling regime for multiple confinement times in high performance discharges with decaying or steady density. With low density, the flat Te profile is also seen to extend into the scrape-off layer. Neutral beam heating is observed in target discharges with relatively flat electron temperature profiles (Tedge ~ Tcore/2), though beam heating is stronger in discharges with higher fueling, higher density, and depressed edge Te. Beam heating produces additional peaking of the Te profile, without degradation of the energy confinement time. Neutral beam heating of target discharges with relatively flat electron temperature profiles similarly results in broad beam heated temperature profiles. Energy confinement in LTX-β generally compares favorably to ohmic and H-mode scalings, frequently exceeding them by factors of 2-4. New and improved diagnostics in LTX-β enable better characterization of this unique regime, including measurements of ion temperature and high field side Thomson scattering profiles. As an initial step toward characterizing turbulence with no Te gradient and roughly equal density and pressure gradient, spectra have been measured in peaked Te discharges using far-forward scattering and fluctuation reflectometry.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725; SC0019239; AC52-07NA27344; SC0023481
OSTI ID:
1968526
Alternate ID(s):
OSTI ID: 1961905; OSTI ID: 1963016; OSTI ID: 1968550
Report Number(s):
LLNL-JRNL-840932
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Vol. 63 Journal Issue: 5; ISSN 0029-5515
Publisher:
IOP PublishingCopyright Statement
Country of Publication:
IAEA
Language:
English

References (41)

Evolution of ELMs, pedestal profiles and fluctuations in the inter-ELM period in NBI- and ECH-dominated discharges in DIII-D journal April 2021
Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment journal May 2017
Toroidal plasma acceleration due to NBI fast ion losses in LTX-β journal July 2021
Neutral beam prompt loss in LTX- β journal October 2021
Ignited spherical tokamaks and plasma regimes with LiWalls journal November 2004
The Plasma Boundary of Magnetic Fusion Devices reference-book December 1999
Lithium–metal infused trenches (LiMIT) for heat removal in fusion devices journal August 2011
Experimental trends of reflectometry frequency spectra emerging from a systematic analysis of the Tore Supra database journal March 2019
First experiments with lithium limiter on FTU journal June 2007
Particle control and plasma performance in the Lithium Tokamak eXperiment journal May 2013
Achieving a long-lived high-beta plasma state by energetic beam injection journal April 2015
A frequency-modulated continuous-wave reflectometer for the Lithium Tokamak Experiment journal May 2017
Chapter 10: The Lithium Wall Fusion Concept book November 2013
Plasma equilibrium reconstructions in the lithium tokamak experiment journal May 2012
Equilibrium reconstruction with 3D eddy currents in the Lithium Tokamak eXperiment journal April 2017
Doppler reflectometry for the investigation of propagating density perturbations journal October 2001
Continuous Improvement of H-Mode Discharge Performance with Progressively Increasing Lithium Coatings in the National Spherical Torus Experiment journal September 2011
Transp software June 2018
Improvement on the plasma performances via application of flowing lithium limiters in EAST tokamak journal January 2020
A tutorial on the basic principles of microwave reflectometry applied to fluctuation measurements in fusion plasmas journal May 2001
Wall conditioning and density control in the reversed field pinch RFX-mod journal May 2013
First liquid lithium limiter biasing experiments in the TJ-II stellarator journal August 2015
Chapter 2: Plasma confinement and transport journal December 1999
Enhancement of Tokamak Fusion Test Reactor performance by lithium conditioning journal May 1996
Development and operation of a high-throughput accurate-wavelength lens-based spectrometer journal November 2014
Neutral Gas Transport Modeling with DEGAS 2 journal January 1994
Lithium, a path to make fusion energy affordable journal May 2021
Performance improvement with plasma edge biasing on SPECTOR journal March 2021
Summary of the FESAC Transformative Enabling Capabilities Panel Report journal March 2019
Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-β (LTX-β) journal June 2023
On lithium walls and the performance of magnetic fusion devices journal May 2003
Millimeter-wave interferometry and far-forward scattering for density fluctuation measurements on LTX- β journal October 2018
Fusion applications for lithium: wall conditioning in magnetic confinement devices journal October 2019
Inversion technique to obtain local ion temperature profiles for an axisymmetric plasma with toroidal and radial velocities journal March 2021
Thermal confinement and transport in spherical tokamaks: a review journal November 2021
The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library journal June 2004
Improved plasma performance in tokamaks with negative magnetic shear journal February 1994
Energy confinement scaling in Tokamaks: some implications of recent experiments with Ohmic and strong auxiliary heating journal January 1984
Energy confinement in the spherical tokamak Globus-M2 with a toroidal magnetic field reaching 0.8 T journal December 2021
Improvement of Plasma Performance with Lithium Wall Conditioning in Aditya Tokamak journal February 2013
Enhanced H-mode pedestals with lithium injection in DIII-D journal May 2015

Similar Records

Investigating the role of edge neutrals in exciting tearing mode activity and achieving flat temperature profiles in LTX-β
Journal Article · Fri Mar 08 00:00:00 EST 2024 · Nuclear Fusion · OSTI ID:1968526

Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment- β  (LTX- β )
Journal Article · Thu Jun 01 00:00:00 EDT 2023 · Nuclear Materials and Energy · OSTI ID:1968526

Estimates of global recycling coefficients for LTX-β discharges
Journal Article · Thu Feb 15 00:00:00 EST 2024 · Physics of Plasmas · OSTI ID:1968526