Implications of NSTX lithium results for magnetic fusion research

M. Ono; M. G. Bell; R. E. Bell; R. Kaita; H. W. Kugel; B. P. Leblanc; J. M. Canik; S. Diem; S. P. Gerhardt; J. Hosea; S. Kaye; D. Mansfield; R. Maingi; J. Menard; S. F. Paul; R. Raman; S. A. Sabbagh; C. H. Skinner; V. Soukhanovskii; G. Taylor

doi:10.1016/j.fusengdes.2010.03.045

Implications of NSTX lithium results for magnetic fusion research

M. Ono, M. G. Bell, R. E. Bell, R. Kaita, H. W. Kugel, B. P. Leblanc, J. M. Canik, S. Diem, S. P. Gerhardt, J. Hosea, S. Kaye, D. Mansfield, R. Maingi, J. Menard, S. F. Paul, R. Raman, S. A. Sabbagh, C. H. Skinner, V. Soukhanovskii, G. Taylor

Fusion Energy Division

Research output: Contribution to journal › Article › peer-review

17 Scopus citations

Abstract

Lithium wall coating techniques have been experimentally explored on National Spherical Torus Experiment (NSTX) for the last five years. The lithium experimentation on NSTX started with a few milligrams of lithium injected into the plasma as pellets and it has evolved to a lithium evaporation system which can evaporate up to ∼100 g of lithium onto the lower divertor plates between lithium re-loadings. The unique feature of the lithium research program on NSTX is that it can investigate the effects of lithium in H-mode divertor plasmas. This lithium evaporation system thus far has produced many intriguing and potentially important results; the latest of these are summarized in a companion paper by H. Kugel. In this paper, we suggest possible implications and applications of the NSTX lithium results on the magnetic fusion research which include electron and global energy confinement improvements, MHD stability enhancement at high beta, edge localized mode (ELM) control, H-mode power threshold reduction, improvements in radio frequency heating and non-inductive plasma start-up performance, innovative divertor solutions and improved operational efficiency.

Original language	English
Pages (from-to)	882-889
Number of pages	8
Journal	Fusion Engineering and Design
Volume	85
Issue number	6
DOIs	https://doi.org/10.1016/j.fusengdes.2010.03.045
State	Published - Nov 2010

Funding

This work was supported by DoE Contract No. DE-AC02-09CH11466.

Funders	Funder number
U.S. Department of Energy	DE-AC02-09CH11466

Keywords

Lithium
NIFS-CRC symposium
Plasma-wall interactions
Tokamaks and spherical tokamaks

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Access to Document

10.1016/j.fusengdes.2010.03.045

Cite this

Ono, M., Bell, M. G., Bell, R. E., Kaita, R., Kugel, H. W., Leblanc, B. P., Canik, J. M., Diem, S., Gerhardt, S. P., Hosea, J., Kaye, S., Mansfield, D., Maingi, R., Menard, J., Paul, S. F., Raman, R., Sabbagh, S. A., Skinner, C. H., Soukhanovskii, V., & Taylor, G. (2010). Implications of NSTX lithium results for magnetic fusion research. Fusion Engineering and Design, 85(6), 882-889. https://doi.org/10.1016/j.fusengdes.2010.03.045

@article{a00d18ac2a8845479e664b36c0f31eb0,

title = "Implications of NSTX lithium results for magnetic fusion research",

abstract = "Lithium wall coating techniques have been experimentally explored on National Spherical Torus Experiment (NSTX) for the last five years. The lithium experimentation on NSTX started with a few milligrams of lithium injected into the plasma as pellets and it has evolved to a lithium evaporation system which can evaporate up to ∼100 g of lithium onto the lower divertor plates between lithium re-loadings. The unique feature of the lithium research program on NSTX is that it can investigate the effects of lithium in H-mode divertor plasmas. This lithium evaporation system thus far has produced many intriguing and potentially important results; the latest of these are summarized in a companion paper by H. Kugel. In this paper, we suggest possible implications and applications of the NSTX lithium results on the magnetic fusion research which include electron and global energy confinement improvements, MHD stability enhancement at high beta, edge localized mode (ELM) control, H-mode power threshold reduction, improvements in radio frequency heating and non-inductive plasma start-up performance, innovative divertor solutions and improved operational efficiency.",

keywords = "Lithium, NIFS-CRC symposium, Plasma-wall interactions, Tokamaks and spherical tokamaks",

author = "M. Ono and Bell, {M. G.} and Bell, {R. E.} and R. Kaita and Kugel, {H. W.} and Leblanc, {B. P.} and Canik, {J. M.} and S. Diem and Gerhardt, {S. P.} and J. Hosea and S. Kaye and D. Mansfield and R. Maingi and J. Menard and Paul, {S. F.} and R. Raman and Sabbagh, {S. A.} and Skinner, {C. H.} and V. Soukhanovskii and G. Taylor",

year = "2010",

month = nov,

doi = "10.1016/j.fusengdes.2010.03.045",

language = "English",

volume = "85",

pages = "882--889",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier",

number = "6",

}

Ono, M, Bell, MG, Bell, RE, Kaita, R, Kugel, HW, Leblanc, BP, Canik, JM, Diem, S, Gerhardt, SP, Hosea, J, Kaye, S, Mansfield, D, Maingi, R, Menard, J, Paul, SF, Raman, R, Sabbagh, SA, Skinner, CH, Soukhanovskii, V & Taylor, G 2010, 'Implications of NSTX lithium results for magnetic fusion research', Fusion Engineering and Design, vol. 85, no. 6, pp. 882-889. https://doi.org/10.1016/j.fusengdes.2010.03.045

TY - JOUR

T1 - Implications of NSTX lithium results for magnetic fusion research

AU - Ono, M.

AU - Bell, M. G.

AU - Bell, R. E.

AU - Kaita, R.

AU - Kugel, H. W.

AU - Leblanc, B. P.

AU - Canik, J. M.

AU - Diem, S.

AU - Gerhardt, S. P.

AU - Hosea, J.

AU - Kaye, S.

AU - Mansfield, D.

AU - Maingi, R.

AU - Menard, J.

AU - Paul, S. F.

AU - Raman, R.

AU - Sabbagh, S. A.

AU - Skinner, C. H.

AU - Soukhanovskii, V.

AU - Taylor, G.

PY - 2010/11

Y1 - 2010/11

N2 - Lithium wall coating techniques have been experimentally explored on National Spherical Torus Experiment (NSTX) for the last five years. The lithium experimentation on NSTX started with a few milligrams of lithium injected into the plasma as pellets and it has evolved to a lithium evaporation system which can evaporate up to ∼100 g of lithium onto the lower divertor plates between lithium re-loadings. The unique feature of the lithium research program on NSTX is that it can investigate the effects of lithium in H-mode divertor plasmas. This lithium evaporation system thus far has produced many intriguing and potentially important results; the latest of these are summarized in a companion paper by H. Kugel. In this paper, we suggest possible implications and applications of the NSTX lithium results on the magnetic fusion research which include electron and global energy confinement improvements, MHD stability enhancement at high beta, edge localized mode (ELM) control, H-mode power threshold reduction, improvements in radio frequency heating and non-inductive plasma start-up performance, innovative divertor solutions and improved operational efficiency.

AB - Lithium wall coating techniques have been experimentally explored on National Spherical Torus Experiment (NSTX) for the last five years. The lithium experimentation on NSTX started with a few milligrams of lithium injected into the plasma as pellets and it has evolved to a lithium evaporation system which can evaporate up to ∼100 g of lithium onto the lower divertor plates between lithium re-loadings. The unique feature of the lithium research program on NSTX is that it can investigate the effects of lithium in H-mode divertor plasmas. This lithium evaporation system thus far has produced many intriguing and potentially important results; the latest of these are summarized in a companion paper by H. Kugel. In this paper, we suggest possible implications and applications of the NSTX lithium results on the magnetic fusion research which include electron and global energy confinement improvements, MHD stability enhancement at high beta, edge localized mode (ELM) control, H-mode power threshold reduction, improvements in radio frequency heating and non-inductive plasma start-up performance, innovative divertor solutions and improved operational efficiency.

KW - Lithium

KW - NIFS-CRC symposium

KW - Plasma-wall interactions

KW - Tokamaks and spherical tokamaks

UR - http://www.scopus.com/inward/record.url?scp=78649491844&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2010.03.045

DO - 10.1016/j.fusengdes.2010.03.045

M3 - Article

AN - SCOPUS:78649491844

SN - 0920-3796

VL - 85

SP - 882

EP - 889

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 6

ER -

Implications of NSTX lithium results for magnetic fusion research

Abstract

Funding

Keywords

UN SDGs

Access to Document

Other files and links

Fingerprint

Cite this