Non-inductive solenoid-less plasma current startup in NSTX using transient CHI

Raman, R.; Mueller, D.; Jarboe, T. R.; Nelson, B. A.; Bell, M.G.; Ono, M.; Bigelow, T.; Kaita, R.; LeBlanc, B.; Lee, K.C.; Maqueda, R. J.; Ménard, J.; Paul, S. F.; Roquemore, L.

doi:10.1088/0029-5515/47/8/009

Cited by 23 publications

(16 citation statements)

References 18 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…One of the major long-term goals of the NSTX-U research program is fully non-inductive plasma current ramp-up and sustainment. Non-inductive plasma start-up will be accomplished through a combination of coaxial helicity injection (CHI) [3], outer poloidal field start-up [4], plasma guns [5], and up to 1 MW of 28 GHz electron cyclotron resonance heating (ECRH). After the plasma becomes overdense for ECRH, the plasma current will be ramped up by bootstrap current and direct current drive using high-harmonic fast-wave heating and neutral beam injection.…”

Section: Introductionmentioning

confidence: 99%

ECRH/EBWH system for NSTX-U

Taylor

Ellis

Harvey

et al. 2012

EPJ Web of Conferences

View full text Add to dashboard Cite

Abstract. The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at an axial toroidal field of up to 1 T, about twice the field available on NSTX. A 28 GHz electron cylotron resonance heating (ECRH) system is currently being planned for NSTX-U. A 1 MW 28 GHz gyrotron will be employed. Intially the system will use short, 10-50 ms, 1 MW pulses for ECRH-assisted discharge start-up. Later the pulse length will be extended to 1-5 s to study electron Bernstein wave heating (EBWH) during the plasma current flat top. A mirror launcher will be used to couple microwave power to the plasma via O-mode to the slow X-mode to EBW (O-X-B) double mode conversion. This paper presents a pre-conceptual design for the ECRH/EBWH system proposed for NSTX-U and includes ray tracing and Fokker-Planck modeling results for 28 GHz ECRH during plasma start-up and EBW heating and current drive during the plasma current flattop of a NSTX-U advanced H-mode plasma scenario.

show abstract

Section: Introductionmentioning

confidence: 99%

ECRH/EBWH system for NSTX-U

Taylor

Ellis

Harvey

et al. 2012

EPJ Web of Conferences

View full text Add to dashboard Cite

show abstract

“…The method has been applied successfully in a number of experiments using different geometries for the applied magnetic fields and voltages [49][50][51][52], and appears particularly useful for current start-up in solenoid-free spherical tokamaks [53].…”

Section: Va Helicity Injectionmentioning

confidence: 99%

Non-Inductive Current Drive

Westerhof

2012

Fusion Science and Technology

View full text Add to dashboard Cite

show abstract

“…is the net flux entering/leaving the volume. The method has been applied successfully in a number of experiments using different geometries for the applied magnetic fields and voltages [49][50][51][52], and appears particularly useful for current start-up in solenoid-free spherical tokamaks [53].…”

Section: Va Helicity Injectionmentioning

confidence: 99%