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. KesselH. 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/inward/citedby.url?scp=85067684331&partnerID=8YFLogxK

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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