Plasma heating and current drive systems for the fusion ignition research experiment (FIRE)

D. W. Swain; M. D. Carter; R. P. Majeski

Plasma heating and current drive systems for the fusion ignition research experiment (FIRE)

D. W. Swain
, M. D. Carter
, R. P. Majeski

Research output: Contribution to conference › Paper › peer-review

Abstract

FIRE is a high-field, burning-plasma tokamak that is being studied as a possible option for future fusion research. Preliminary parameters for this machine are R_o ≈ 2 m, a ≈ 0.5 m, B_o ≈ 10 T, and I_p ≈ 6 MA. Magnetic field coils are to be made of copper and pre-cooled with LN₂ before each shot. The flat-top pulse length desired is ≥ 10s. Ion cyclotron and lower hybrid rf systems will be used for heating and current drive. Present specifications call for 30 MW of ion cyclotron heating power, with 25 MW of lower hybrid power as an upgrade option.

Original language	English (US)
Pages	467-470
Number of pages	4
State	Published - 1999
Externally published	Yes
Event	18th IEEE/NPSS Symposium on Fusion Engineering (SOFE99) - Albuquerque, NM, USA Duration: Oct 25 1999 → Oct 29 1999

Other

Other	18th IEEE/NPSS Symposium on Fusion Engineering (SOFE99)
City	Albuquerque, NM, USA
Period	10/25/99 → 10/29/99

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Cite this

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title = "Plasma heating and current drive systems for the fusion ignition research experiment (FIRE)",

abstract = "FIRE is a high-field, burning-plasma tokamak that is being studied as a possible option for future fusion research. Preliminary parameters for this machine are Ro ≈ 2 m, a ≈ 0.5 m, Bo ≈ 10 T, and Ip ≈ 6 MA. Magnetic field coils are to be made of copper and pre-cooled with LN2 before each shot. The flat-top pulse length desired is ≥ 10s. Ion cyclotron and lower hybrid rf systems will be used for heating and current drive. Present specifications call for 30 MW of ion cyclotron heating power, with 25 MW of lower hybrid power as an upgrade option.",

author = "Swain, \{D. W.\} and Carter, \{M. D.\} and Majeski, \{R. P.\}",

year = "1999",

language = "English (US)",

pages = "467--470",

note = "18th IEEE/NPSS Symposium on Fusion Engineering (SOFE99) ; Conference date: 25-10-1999 Through 29-10-1999",

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TY - CONF

T1 - Plasma heating and current drive systems for the fusion ignition research experiment (FIRE)

AU - Swain, D. W.

AU - Carter, M. D.

AU - Majeski, R. P.

PY - 1999

Y1 - 1999

N2 - FIRE is a high-field, burning-plasma tokamak that is being studied as a possible option for future fusion research. Preliminary parameters for this machine are Ro ≈ 2 m, a ≈ 0.5 m, Bo ≈ 10 T, and Ip ≈ 6 MA. Magnetic field coils are to be made of copper and pre-cooled with LN2 before each shot. The flat-top pulse length desired is ≥ 10s. Ion cyclotron and lower hybrid rf systems will be used for heating and current drive. Present specifications call for 30 MW of ion cyclotron heating power, with 25 MW of lower hybrid power as an upgrade option.

AB - FIRE is a high-field, burning-plasma tokamak that is being studied as a possible option for future fusion research. Preliminary parameters for this machine are Ro ≈ 2 m, a ≈ 0.5 m, Bo ≈ 10 T, and Ip ≈ 6 MA. Magnetic field coils are to be made of copper and pre-cooled with LN2 before each shot. The flat-top pulse length desired is ≥ 10s. Ion cyclotron and lower hybrid rf systems will be used for heating and current drive. Present specifications call for 30 MW of ion cyclotron heating power, with 25 MW of lower hybrid power as an upgrade option.

UR - https://www.scopus.com/pages/publications/0033295890

UR - https://www.scopus.com/pages/publications/0033295890#tab=citedBy

M3 - Paper

AN - SCOPUS:0033295890

SP - 467

EP - 470

T2 - 18th IEEE/NPSS Symposium on Fusion Engineering (SOFE99)

Y2 - 25 October 1999 through 29 October 1999

ER -

Plasma heating and current drive systems for the fusion ignition research experiment (FIRE)

Abstract

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All Science Journal Classification (ASJC) codes

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