Divertor pumping and other reactor application issues for H-mode

R. D. Stambaugh; S. L. Allen; N. H. Brooks; D. N. Hill; D. L. Hillis; A. W. Hyatt; G. L. Jackson; S. Konoshima; E. A. Lazarus; A. W. Leonard; S. I. Lippmann; M. A. Mahdavi; R. Maingi; M. M. Menon; T. H. Osborne; T. W. Petrie; G. D. Porter; M. E. Rensink; M. J. Schaffer; D. P. Schissel; G. M. Staebler; M. R. Wade; R. D. Wood

doi:10.1088/0741-3335/36/7A/036

Divertor pumping and other reactor application issues for H-mode

R. D. Stambaugh, S. L. Allen, N. H. Brooks, D. N. Hill, D. L. Hillis, A. W. Hyatt, G. L. Jackson, S. Konoshima, E. A. Lazarus, A. W. Leonard, S. I. Lippmann, M. A. Mahdavi, R. Maingi, M. M. Menon, T. H. Osborne, T. W. Petrie, G. D. Porter, M. E. Rensink, M. J. Schaffer, D. P. SchisselG. M. Staebler, M. R. Wade, R. D. Wood

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Abstract

We summarize results from DIII-D in regard to issues for reactor application of H-mode. Recently, DIII-D has begun to operate a cryopump (D ₂ pumping speed =31,000 l/s at a pressure of 2 mTorr). Initial results are very favorable for density control in H-mode. The plasma density could be reduced by 50%. Energy confinement is unchanged so the temperature rises in proportion to the density drop. Ability to access these less collisional plasmas in H-mode is favorable to current drive application. With the all-graphite wall, impurity accumulation has been eliminated. The exceedingly good confinement of VH-mode offers the possibility of retaining good confinement while radiating copious power from the plasma edge using injected noble gas impurities.

Original language	English
Article number	036
Pages (from-to)	A249-A254
Journal	Plasma Physics and Controlled Fusion
Volume	36
Issue number	7 A
DOIs	https://doi.org/10.1088/0741-3335/36/7A/036
State	Published - 1994
Externally published	Yes

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Stambaugh, R. D., Allen, S. L., Brooks, N. H., Hill, D. N., Hillis, D. L., Hyatt, A. W., Jackson, G. L., Konoshima, S., Lazarus, E. A., Leonard, A. W., Lippmann, S. I., Mahdavi, M. A., Maingi, R., Menon, M. M., Osborne, T. H., Petrie, T. W., Porter, G. D., Rensink, M. E., Schaffer, M. J., ... Wood, R. D. (1994). Divertor pumping and other reactor application issues for H-mode. Plasma Physics and Controlled Fusion, 36(7 A), A249-A254. Article 036. https://doi.org/10.1088/0741-3335/36/7A/036

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title = "Divertor pumping and other reactor application issues for H-mode",

abstract = "We summarize results from DIII-D in regard to issues for reactor application of H-mode. Recently, DIII-D has begun to operate a cryopump (D 2 pumping speed =31,000 l/s at a pressure of 2 mTorr). Initial results are very favorable for density control in H-mode. The plasma density could be reduced by 50%. Energy confinement is unchanged so the temperature rises in proportion to the density drop. Ability to access these less collisional plasmas in H-mode is favorable to current drive application. With the all-graphite wall, impurity accumulation has been eliminated. The exceedingly good confinement of VH-mode offers the possibility of retaining good confinement while radiating copious power from the plasma edge using injected noble gas impurities.",

author = "Stambaugh, {R. D.} and Allen, {S. L.} and Brooks, {N. H.} and Hill, {D. N.} and Hillis, {D. L.} and Hyatt, {A. W.} and Jackson, {G. L.} and S. Konoshima and Lazarus, {E. A.} and Leonard, {A. W.} and Lippmann, {S. I.} and Mahdavi, {M. A.} and R. Maingi and Menon, {M. M.} and Osborne, {T. H.} and Petrie, {T. W.} and Porter, {G. D.} and Rensink, {M. E.} and Schaffer, {M. J.} and Schissel, {D. P.} and Staebler, {G. M.} and Wade, {M. R.} and Wood, {R. D.}",

year = "1994",

doi = "10.1088/0741-3335/36/7A/036",

language = "English",

volume = "36",

pages = "A249--A254",

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Stambaugh, RD, Allen, SL, Brooks, NH, Hill, DN, Hillis, DL, Hyatt, AW, Jackson, GL, Konoshima, S, Lazarus, EA, Leonard, AW, Lippmann, SI, Mahdavi, MA, Maingi, R, Menon, MM, Osborne, TH, Petrie, TW, Porter, GD, Rensink, ME, Schaffer, MJ, Schissel, DP, Staebler, GM , Wade, MR & Wood, RD 1994, 'Divertor pumping and other reactor application issues for H-mode', Plasma Physics and Controlled Fusion, vol. 36, no. 7 A, 036, pp. A249-A254. https://doi.org/10.1088/0741-3335/36/7A/036

TY - JOUR

T1 - Divertor pumping and other reactor application issues for H-mode

AU - Stambaugh, R. D.

AU - Allen, S. L.

AU - Brooks, N. H.

AU - Hill, D. N.

AU - Hillis, D. L.

AU - Hyatt, A. W.

AU - Jackson, G. L.

AU - Konoshima, S.

AU - Lazarus, E. A.

AU - Leonard, A. W.

AU - Lippmann, S. I.

AU - Mahdavi, M. A.

AU - Maingi, R.

AU - Menon, M. M.

AU - Osborne, T. H.

AU - Petrie, T. W.

AU - Porter, G. D.

AU - Rensink, M. E.

AU - Schaffer, M. J.

AU - Schissel, D. P.

AU - Staebler, G. M.

AU - Wade, M. R.

AU - Wood, R. D.

PY - 1994

Y1 - 1994

N2 - We summarize results from DIII-D in regard to issues for reactor application of H-mode. Recently, DIII-D has begun to operate a cryopump (D 2 pumping speed =31,000 l/s at a pressure of 2 mTorr). Initial results are very favorable for density control in H-mode. The plasma density could be reduced by 50%. Energy confinement is unchanged so the temperature rises in proportion to the density drop. Ability to access these less collisional plasmas in H-mode is favorable to current drive application. With the all-graphite wall, impurity accumulation has been eliminated. The exceedingly good confinement of VH-mode offers the possibility of retaining good confinement while radiating copious power from the plasma edge using injected noble gas impurities.

AB - We summarize results from DIII-D in regard to issues for reactor application of H-mode. Recently, DIII-D has begun to operate a cryopump (D 2 pumping speed =31,000 l/s at a pressure of 2 mTorr). Initial results are very favorable for density control in H-mode. The plasma density could be reduced by 50%. Energy confinement is unchanged so the temperature rises in proportion to the density drop. Ability to access these less collisional plasmas in H-mode is favorable to current drive application. With the all-graphite wall, impurity accumulation has been eliminated. The exceedingly good confinement of VH-mode offers the possibility of retaining good confinement while radiating copious power from the plasma edge using injected noble gas impurities.

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U2 - 10.1088/0741-3335/36/7A/036

DO - 10.1088/0741-3335/36/7A/036

M3 - Article

AN - SCOPUS:0028464897

SN - 0741-3335

VL - 36

SP - A249-A254

JO - Plasma Physics and Controlled Fusion

JF - Plasma Physics and Controlled Fusion

IS - 7 A

M1 - 036

ER -

Divertor pumping and other reactor application issues for H-mode

Abstract

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