The ARIES-III D-3He tokamak-reactor study

C. G. Bathke; J. P. Blanchard; L. Bromberg; J. Brooks; E. T. Cheng; D. R. Cohn; D. A. Ehst; L. A. El-Guebaly; G. A. Emmert; T. J. Dolan; P. Gierszewski; S. P. Grotz; M. Z. Hasan; J. S. Herring; S. K. Ho; R. Hollies; J. A. Holmes; E. Ibrahim; S. A. Jardin; C. E. Kessel; H. Y. Khater; R. A. Krakowski; G. L. Kulcinski; J. Mandrekas; T. K. Mau; G. H. Miley; R. L. Miller; E. A. Mogahed; E. Reis; J. F. Santanus; M. Sawan; J. Schultz; K. R. Schultz; S. Sharafat; D. Steiner; D. J. Strickler; I. N. Sviatoslavsky; D. K. Sze; P. Titus; M. Valenti; K. A. Werley; J. H. Whealton; J. E.C. Williams; L. J. Wittenberg; C. P.C. Wong

doi:10.1109/FUSION.1991.218914

The ARIES-III D-3He tokamak-reactor study

C. G. Bathke
, J. P. Blanchard
, L. Bromberg
, J. Brooks
, E. T. Cheng
, D. R. Cohn
, D. A. Ehst
, L. A. El-Guebaly
, G. A. Emmert
, T. J. Dolan
, P. Gierszewski
, S. P. Grotz
, M. Z. Hasan
, J. S. Herring
, S. K. Ho
, R. Hollies
, J. A. Holmes
, E. Ibrahim
, S. A. Jardin
, C. E. Kessel

H. Y. Khater, R. A. Krakowski, G. L. Kulcinski, J. Mandrekas, T. K. Mau, G. H. Miley, R. L. Miller, E. A. Mogahed, E. Reis, J. F. Santanus, M. Sawan, J. Schultz, K. R. Schultz, S. Sharafat, D. Steiner, D. J. Strickler, I. N. Sviatoslavsky, D. K. Sze, P. Titus, M. Valenti, K. A. Werley, J. H. Whealton, J. E.C. Williams, L. J. Wittenberg, C. P.C. Wong

PPPL Theory

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

4 Scopus citations

Abstract

The ARIES study is a community effort to develop several visions of tokamaks as fusion power reactors. The aims are: To determine their potential economics, safety, and environmental features; to identify the physics and technology areas with the highest leverage for achieving the best tokamak reactor. The ARIES-III design is the subject of this paper. The ARIES-III research activity focuses on the potential of D-3He-fueled tokamaks because they may offer even greater environmental and safety advantages than DT-fueled reactors. Analyses have shown that the plasma power-balance window for D-3He tokamak reactors is small and requires a first wall (or coating) that is highly reflective to synchrotron radiation and small values of rajfc/r£ (the ratio of ash-particle to energy confinement times in the core plasma). Both first and second stability regimes of operation have been considered. The second stability regime is chosen for the ARIES-III design point because the reactor can operate at a higher value of t^Jtb - 2 (twice that of a first stability version), and because it has a reduced plasma current (30 MA), magnetic field at the coil (14 T), mass, and cost (also compared to a first-stability D-3He reactor). The major and minor radii are, respectively, 7.5 and 2.5 m. In this paper, a description of the ARIES-III research effort is presented and the general features of the ARIES-III reactor are described. The plasma engineering and fusion-power-core design are summarized, including the major results, the key technical issues, and the central conclusions.

Original language	English (US)
Title of host publication	Proceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991
Publisher	Institute of Electrical and Electronics Engineers Inc.
Pages	213-218
Number of pages	6
ISBN (Electronic)	0780301323
DOIs	https://doi.org/10.1109/FUSION.1991.218914
State	Published - 1991
Event	14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991 - San Diego, United States Duration: Sep 30 1991 → Oct 3 1991

Publication series

Name	Proceedings - Symposium on Fusion Engineering

Conference

Conference	14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991
Country/Territory	United States
City	San Diego
Period	9/30/91 → 10/3/91

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Access to Document

10.1109/FUSION.1991.218914

Cite this

Bathke, C. G., Blanchard, J. P., Bromberg, L., Brooks, J., Cheng, E. T., Cohn, D. R., Ehst, D. A., El-Guebaly, L. A., Emmert, G. A., Dolan, T. J., Gierszewski, P., Grotz, S. P., Hasan, M. Z., Herring, J. S., Ho, S. K., Hollies, R., Holmes, J. A., Ibrahim, E., Jardin, S. A., ... Wong, C. P. C. (1991). The ARIES-III D-3He tokamak-reactor study. In Proceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991 (pp. 213-218). Article 218914 (Proceedings - Symposium on Fusion Engineering). Institute of Electrical and Electronics Engineers Inc.. https://doi.org/10.1109/FUSION.1991.218914

@inproceedings{d080647d8a794134885c20d382878c1f,

title = "The ARIES-III D-3He tokamak-reactor study",

abstract = "The ARIES study is a community effort to develop several visions of tokamaks as fusion power reactors. The aims are: To determine their potential economics, safety, and environmental features; to identify the physics and technology areas with the highest leverage for achieving the best tokamak reactor. The ARIES-III design is the subject of this paper. The ARIES-III research activity focuses on the potential of D-3He-fueled tokamaks because they may offer even greater environmental and safety advantages than DT-fueled reactors. Analyses have shown that the plasma power-balance window for D-3He tokamak reactors is small and requires a first wall (or coating) that is highly reflective to synchrotron radiation and small values of rajfc/r£ (the ratio of ash-particle to energy confinement times in the core plasma). Both first and second stability regimes of operation have been considered. The second stability regime is chosen for the ARIES-III design point because the reactor can operate at a higher value of t\textasciicircum{}Jtb - 2 (twice that of a first stability version), and because it has a reduced plasma current (30 MA), magnetic field at the coil (14 T), mass, and cost (also compared to a first-stability D-3He reactor). The major and minor radii are, respectively, 7.5 and 2.5 m. In this paper, a description of the ARIES-III research effort is presented and the general features of the ARIES-III reactor are described. The plasma engineering and fusion-power-core design are summarized, including the major results, the key technical issues, and the central conclusions.",

author = "Bathke, \{C. G.\} and Blanchard, \{J. P.\} and L. Bromberg and J. Brooks and Cheng, \{E. T.\} and Cohn, \{D. R.\} and Ehst, \{D. A.\} and El-Guebaly, \{L. A.\} and Emmert, \{G. A.\} and Dolan, \{T. J.\} and P. Gierszewski and Grotz, \{S. P.\} and Hasan, \{M. Z.\} and Herring, \{J. S.\} and Ho, \{S. K.\} and R. Hollies and Holmes, \{J. A.\} and E. Ibrahim and Jardin, \{S. A.\} and Kessel, \{C. E.\} and Khater, \{H. Y.\} and Krakowski, \{R. A.\} and Kulcinski, \{G. L.\} and J. Mandrekas and Mau, \{T. K.\} and Miley, \{G. H.\} and Miller, \{R. L.\} and Mogahed, \{E. A.\} and E. Reis and Santanus, \{J. F.\} and M. Sawan and J. Schultz and Schultz, \{K. R.\} and S. Sharafat and D. Steiner and Strickler, \{D. J.\} and Sviatoslavsky, \{I. N.\} and Sze, \{D. K.\} and P. Titus and M. Valenti and Werley, \{K. A.\} and Whealton, \{J. H.\} and Williams, \{J. E.C.\} and Wittenberg, \{L. J.\} and Wong, \{C. P.C.\}",

note = "Publisher Copyright: {\textcopyright} 1991 IEEE.; 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991 ; Conference date: 30-09-1991 Through 03-10-1991",

year = "1991",

doi = "10.1109/FUSION.1991.218914",

language = "English (US)",

series = "Proceedings - Symposium on Fusion Engineering",

publisher = "Institute of Electrical and Electronics Engineers Inc.",

pages = "213--218",

booktitle = "Proceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991",

address = "United States",

}

Bathke, CG, Blanchard, JP, Bromberg, L, Brooks, J, Cheng, ET, Cohn, DR, Ehst, DA, El-Guebaly, LA, Emmert, GA, Dolan, TJ, Gierszewski, P, Grotz, SP, Hasan, MZ, Herring, JS, Ho, SK, Hollies, R, Holmes, JA, Ibrahim, E, Jardin, SA, Kessel, CE, Khater, HY, Krakowski, RA, Kulcinski, GL, Mandrekas, J, Mau, TK, Miley, GH, Miller, RL, Mogahed, EA, Reis, E, Santanus, JF, Sawan, M, Schultz, J, Schultz, KR, Sharafat, S, Steiner, D, Strickler, DJ, Sviatoslavsky, IN, Sze, DK, Titus, P, Valenti, M, Werley, KA, Whealton, JH, Williams, JEC, Wittenberg, LJ & Wong, CPC 1991, The ARIES-III D-3He tokamak-reactor study. in Proceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991., 218914, Proceedings - Symposium on Fusion Engineering, Institute of Electrical and Electronics Engineers Inc., pp. 213-218, 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991, San Diego, United States, 9/30/91. https://doi.org/10.1109/FUSION.1991.218914

The ARIES-III D-3He tokamak-reactor study. / Bathke, C. G.; Blanchard, J. P.; Bromberg, L. et al.
Proceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991. Institute of Electrical and Electronics Engineers Inc., 1991. p. 213-218 218914 (Proceedings - Symposium on Fusion Engineering).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

TY - GEN

T1 - The ARIES-III D-3He tokamak-reactor study

AU - Bathke, C. G.

AU - Blanchard, J. P.

AU - Bromberg, L.

AU - Brooks, J.

AU - Cheng, E. T.

AU - Cohn, D. R.

AU - Ehst, D. A.

AU - El-Guebaly, L. A.

AU - Emmert, G. A.

AU - Dolan, T. J.

AU - Gierszewski, P.

AU - Grotz, S. P.

AU - Hasan, M. Z.

AU - Herring, J. S.

AU - Ho, S. K.

AU - Hollies, R.

AU - Holmes, J. A.

AU - Ibrahim, E.

AU - Jardin, S. A.

AU - Kessel, C. E.

AU - Khater, H. Y.

AU - Krakowski, R. A.

AU - Kulcinski, G. L.

AU - Mandrekas, J.

AU - Mau, T. K.

AU - Miley, G. H.

AU - Miller, R. L.

AU - Mogahed, E. A.

AU - Reis, E.

AU - Santanus, J. F.

AU - Sawan, M.

AU - Schultz, J.

AU - Schultz, K. R.

AU - Sharafat, S.

AU - Steiner, D.

AU - Strickler, D. J.

AU - Sviatoslavsky, I. N.

AU - Sze, D. K.

AU - Titus, P.

AU - Valenti, M.

AU - Werley, K. A.

AU - Whealton, J. H.

AU - Williams, J. E.C.

AU - Wittenberg, L. J.

AU - Wong, C. P.C.

PY - 1991

Y1 - 1991

N2 - The ARIES study is a community effort to develop several visions of tokamaks as fusion power reactors. The aims are: To determine their potential economics, safety, and environmental features; to identify the physics and technology areas with the highest leverage for achieving the best tokamak reactor. The ARIES-III design is the subject of this paper. The ARIES-III research activity focuses on the potential of D-3He-fueled tokamaks because they may offer even greater environmental and safety advantages than DT-fueled reactors. Analyses have shown that the plasma power-balance window for D-3He tokamak reactors is small and requires a first wall (or coating) that is highly reflective to synchrotron radiation and small values of rajfc/r£ (the ratio of ash-particle to energy confinement times in the core plasma). Both first and second stability regimes of operation have been considered. The second stability regime is chosen for the ARIES-III design point because the reactor can operate at a higher value of t^Jtb - 2 (twice that of a first stability version), and because it has a reduced plasma current (30 MA), magnetic field at the coil (14 T), mass, and cost (also compared to a first-stability D-3He reactor). The major and minor radii are, respectively, 7.5 and 2.5 m. In this paper, a description of the ARIES-III research effort is presented and the general features of the ARIES-III reactor are described. The plasma engineering and fusion-power-core design are summarized, including the major results, the key technical issues, and the central conclusions.

AB - The ARIES study is a community effort to develop several visions of tokamaks as fusion power reactors. The aims are: To determine their potential economics, safety, and environmental features; to identify the physics and technology areas with the highest leverage for achieving the best tokamak reactor. The ARIES-III design is the subject of this paper. The ARIES-III research activity focuses on the potential of D-3He-fueled tokamaks because they may offer even greater environmental and safety advantages than DT-fueled reactors. Analyses have shown that the plasma power-balance window for D-3He tokamak reactors is small and requires a first wall (or coating) that is highly reflective to synchrotron radiation and small values of rajfc/r£ (the ratio of ash-particle to energy confinement times in the core plasma). Both first and second stability regimes of operation have been considered. The second stability regime is chosen for the ARIES-III design point because the reactor can operate at a higher value of t^Jtb - 2 (twice that of a first stability version), and because it has a reduced plasma current (30 MA), magnetic field at the coil (14 T), mass, and cost (also compared to a first-stability D-3He reactor). The major and minor radii are, respectively, 7.5 and 2.5 m. In this paper, a description of the ARIES-III research effort is presented and the general features of the ARIES-III reactor are described. The plasma engineering and fusion-power-core design are summarized, including the major results, the key technical issues, and the central conclusions.

UR - https://www.scopus.com/pages/publications/85067684331

UR - https://www.scopus.com/pages/publications/85067684331#tab=citedBy

U2 - 10.1109/FUSION.1991.218914

DO - 10.1109/FUSION.1991.218914

M3 - Conference contribution

AN - SCOPUS:85067684331

T3 - Proceedings - Symposium on Fusion Engineering

SP - 213

EP - 218

BT - Proceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991

PB - Institute of Electrical and Electronics Engineers Inc.

T2 - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991

Y2 - 30 September 1991 through 3 October 1991

ER -

The ARIES-III D-3He tokamak-reactor study

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