Spherical Tokamak Plasma Science and Fusion Energy Component Testing
スポンサーリンク
概要
- 論文の詳細を見る
Recent progress(1) in plasma science of the Spherical Tokamak (or Spherical Torus, ST)(2) has indicated relatively robust plasma conditions in a broad number of topical area including strong shaping, stability limits, energy confinement, self-driven current, and sustainment. This progress has enabled an extensive update of the plasma science and fusion engineering conditions of a Component Test Facility (CTF)(3), which is potentially a necessary step in the development of practical fusion energy. The chamber systems testing conditions in a CTF are characterized by high fusion neutron fluxes Γn > 4.4×1013 n/s/cm2, over size-scale > 105 cm2 and depth-scale > 50 cm, delivering > 3 accumulated displacement per atom (dpa) per year(4). Such chamber conditions are calculated to be achievable in a CTF with R0 = 1.2 m, A = 1.5, elongation - 3, Ip - 9 MA, BT - 2.5 T, producing a driven fusion burn using 36 MW of combined neutral beam and RF power. The ST CTF will test the life time of single-turn, copper alloy center leg for the toroidal field coil without an induction solenoid and neutron shielding, and require physics data on solenoid-free plasma current initiation, ramp-up, and sustainment to multiple MA level. A new systems code that combines the key required plasma and engineering science conditions of CTF has been prepared and utilized as part of this study. The results show high potential for a family of relatively low cost CTF devices to suit a range of fusion engineering science test missions.
著者
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Bell R.
Princeton University
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Gates D.
Princeton University
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Kessel C.
Princeton University
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LeBlanc B.
Princeton University
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Menard J.
Princeton University
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Neumeyer C.
Princeton University
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Synakowski E.
Princeton University
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Grisham L.
Princeton University
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Mitarai O.
Kyushu Tokai University
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Schmidt J.
Princeton University
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Peng Y.-K.
Princeton Plasma Physics Laboratory
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Fogarty P.
Oak Ridge National Laboratory
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Burgess T.
Oak Ridge National Laboratory
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Strickler D.
Oak Ridge National Laboratory
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Tsai J.
Princeton Plasma Physics Laboratory
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Rutherford P.
Princeton Plasma Physics Laboratory
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Mikkelsen D.
Princeton Plasma Physics Laboratory
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Sabbagh S.
Princeton Plasma Physics Laboratory
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El-Guebaly L.
University of Wisconsin
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Leblanc B.
Princeton Plasma Physics Lab. New Jersey Usa
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Neumeyer C.
Princeton Plasma Physics Laboratory
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Menard J.
Princeton Plasma Physics Laboratory
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LeBlanc B.
Princeton Plasma Physics Laboratory
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Peng Y.
Princeton Plasma Physics Laboratory
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Gates D.
Princeton Plasma Physics Laboratory
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Schmidt J.
Princeton Plasma Physics Laboratory
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Kessel C.
Princeton Plasma Physics Laboratory
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Grisham L.
Princeton Plasma Physics Laboratory
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Synakowski E.
Princeton Plasma Physics Laboratory
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Bell R.
Princeton Plasma Physics Laboratory
関連論文
- Status and Plans for the National Spherical Torus Experimental Research Facility
- Spherical Tokamak Plasma Science and Fusion Energy Component Testing
- Plasma Shape Reconstruction of Spherical Tokamak using CCS Method