Impurity transport in ohmic and neutral-beam-heated TFTR discharges

B. C. Stratton; S. A. Cohen; F. P. Boody; C. E. Bush; R. Ellis; R. J. Fonck; E. Fredrickson; R. J. Groebner; K. W. Hill; R. A. Hulse; E. S. Marmar; A. T. Ramsey; J. F. Schivell; S. S. Sesnic; J. Timberlake

doi:10.1016/0022-3115(87)90404-1

Impurity transport in ohmic and neutral-beam-heated TFTR discharges

B. C. Stratton, S. A. Cohen, F. P. Boody, C. E. Bush, R. Ellis, R. J. Fonck, E. Fredrickson, R. J. Groebner, K. W. Hill, R. A. Hulse, E. S. Marmar, A. T. Ramsey, J. F. Schivell, S. S. Sesnic, J. Timberlake

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Abstract

Impurity transport has been studied in ohmic and neutral-beam-heated TFTR discharges by observation and numerical modeling of time evolutions of emissions from germanium injected using the laser-blowoff method. VUV spectral lines, the total radiated power, and soft X-ray intensities are compared with code predictions in which the impurity flux is assumed to have diffusive and convective terms. In plasmas with I_p = 1.4 MA and n_e ≈ 2.5 × 10¹³ cm^-3, no difference in transport between ohmic and beam-heated discharges is observed. At I_p = 0.7 MA and n_e ≈ 1.0 × 10¹³ cm^-3, a three-fold increase in the diffusion coefficient is found during beam heating.

Original language	English (US)
Pages (from-to)	587-591
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	145-147
Issue number	C
DOIs	https://doi.org/10.1016/0022-3115(87)90404-1
State	Published - Feb 2 1987

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

Keywords

convection
diffusion coefficients
impurity dynamics
impurity fluxes

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10.1016/0022-3115(87)90404-1

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Stratton, B. C., Cohen, S. A., Boody, F. P., Bush, C. E., Ellis, R., Fonck, R. J., Fredrickson, E., Groebner, R. J., Hill, K. W., Hulse, R. A., Marmar, E. S., Ramsey, A. T., Schivell, J. F., Sesnic, S. S., & Timberlake, J. (1987). Impurity transport in ohmic and neutral-beam-heated TFTR discharges. Journal of Nuclear Materials, 145-147(C), 587-591. https://doi.org/10.1016/0022-3115(87)90404-1

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title = "Impurity transport in ohmic and neutral-beam-heated TFTR discharges",

abstract = "Impurity transport has been studied in ohmic and neutral-beam-heated TFTR discharges by observation and numerical modeling of time evolutions of emissions from germanium injected using the laser-blowoff method. VUV spectral lines, the total radiated power, and soft X-ray intensities are compared with code predictions in which the impurity flux is assumed to have diffusive and convective terms. In plasmas with Ip = 1.4 MA and ne ≈ 2.5 × 1013 cm-3, no difference in transport between ohmic and beam-heated discharges is observed. At Ip = 0.7 MA and ne ≈ 1.0 × 1013 cm-3, a three-fold increase in the diffusion coefficient is found during beam heating.",

keywords = "convection, diffusion coefficients, impurity dynamics, impurity fluxes",

author = "Stratton, {B. C.} and Cohen, {S. A.} and Boody, {F. P.} and Bush, {C. E.} and R. Ellis and Fonck, {R. J.} and E. Fredrickson and Groebner, {R. J.} and Hill, {K. W.} and Hulse, {R. A.} and Marmar, {E. S.} and Ramsey, {A. T.} and Schivell, {J. F.} and Sesnic, {S. S.} and J. Timberlake",

note = "Funding Information: We would like to thank R. Goldston, D. Grove, R. Hawryluk, D. Meadea nd K. Young for their supporto f this work, the TFTR operatingp hysicistsa nd technical staff, and B. Grek, D. Johnson, B. LeBlanc and D. McNeil1 for providing thomson scatteringd ata. This work was supportedb y US DOE contract no. DE-AC02-76-CHO-3073.",

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doi = "10.1016/0022-3115(87)90404-1",

language = "English (US)",

volume = "145-147",

pages = "587--591",

journal = "Journal of Nuclear Materials",

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T1 - Impurity transport in ohmic and neutral-beam-heated TFTR discharges

AU - Stratton, B. C.

AU - Cohen, S. A.

AU - Boody, F. P.

AU - Bush, C. E.

AU - Ellis, R.

AU - Fonck, R. J.

AU - Fredrickson, E.

AU - Groebner, R. J.

AU - Hill, K. W.

AU - Hulse, R. A.

AU - Marmar, E. S.

AU - Ramsey, A. T.

AU - Schivell, J. F.

AU - Sesnic, S. S.

AU - Timberlake, J.

N1 - Funding Information: We would like to thank R. Goldston, D. Grove, R. Hawryluk, D. Meadea nd K. Young for their supporto f this work, the TFTR operatingp hysicistsa nd technical staff, and B. Grek, D. Johnson, B. LeBlanc and D. McNeil1 for providing thomson scatteringd ata. This work was supportedb y US DOE contract no. DE-AC02-76-CHO-3073.

PY - 1987/2/2

Y1 - 1987/2/2

N2 - Impurity transport has been studied in ohmic and neutral-beam-heated TFTR discharges by observation and numerical modeling of time evolutions of emissions from germanium injected using the laser-blowoff method. VUV spectral lines, the total radiated power, and soft X-ray intensities are compared with code predictions in which the impurity flux is assumed to have diffusive and convective terms. In plasmas with Ip = 1.4 MA and ne ≈ 2.5 × 1013 cm-3, no difference in transport between ohmic and beam-heated discharges is observed. At Ip = 0.7 MA and ne ≈ 1.0 × 1013 cm-3, a three-fold increase in the diffusion coefficient is found during beam heating.

AB - Impurity transport has been studied in ohmic and neutral-beam-heated TFTR discharges by observation and numerical modeling of time evolutions of emissions from germanium injected using the laser-blowoff method. VUV spectral lines, the total radiated power, and soft X-ray intensities are compared with code predictions in which the impurity flux is assumed to have diffusive and convective terms. In plasmas with Ip = 1.4 MA and ne ≈ 2.5 × 1013 cm-3, no difference in transport between ohmic and beam-heated discharges is observed. At Ip = 0.7 MA and ne ≈ 1.0 × 1013 cm-3, a three-fold increase in the diffusion coefficient is found during beam heating.

KW - convection

KW - diffusion coefficients

KW - impurity dynamics

KW - impurity fluxes

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VL - 145-147

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - C

ER -

Impurity transport in ohmic and neutral-beam-heated TFTR discharges

Abstract

All Science Journal Classification (ASJC) codes

Keywords

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