Fusion Engineering and Plasma Science Conditions of Spherical Torus Component Test Facility
| Autor: | R.E. Bell, Paul H Rutherford, Edward T. Cheng, P.J. Fogarty, Yueng Kay Martin Peng, Dennis J Strickler, C.E. Kessel, J. Tsai, Larry R. Grisham, Jonathan Menard, Laila El-Guebaly, David Gates, S.A. Sabbagh, D. R. Mikkelsen, Thomas W Burgess, C. A. Neumeyer, Osamu Mitarai, B.E. Nelson, B.P. LeBlanc, E. J. Synakowski, J. A. Schmidt |
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| Rok vydání: | 2005 |
| Předmět: |
Physics
Nuclear and High Energy Physics Thermonuclear fusion 020209 energy Mechanical Engineering Center (category theory) Magnetic confinement fusion Torus 02 engineering and technology Plasma Spherical tokamak Fusion power 01 natural sciences 010305 fluids & plasmas Nuclear physics Nuclear Energy and Engineering 0103 physical sciences 0202 electrical engineering electronic engineering information engineering General Materials Science Neutron Atomic physics Civil and Structural Engineering |
| Zdroj: | Fusion Science and Technology. 47:370-383 |
| ISSN: | 1943-7641 1536-1055 |
| Popis: | A broadly based study of the fusion engineering and plasma science conditions of a Component Test Facility (CTF), using the Spherical Torus or Spherical Tokamak (ST) configuration, have been carried out. The chamber systems testing conditions in a CTF are characterized by high fusion neutron fluxes {gamma}{sub n} > 4.4 x 10{sup 13} n/s/cm{sup 2}, over size scales > 10{sup 5} cm{sup 2} and depth scales > 50 cm, delivering > 3 accumulated displacement per atom (dpa) per year. The desired chamber conditions can be provided by a CTF with R{sub 0} 1.2 m, A = 1.5, elongation {approx} 3, I{sub p} {approx} 9 MA, B{sub T} {approx} 2.5 T, producing a driven fusion burn using 36 MW of combined neutral beam and RF power. Relatively robust ST plasma conditions are adequate, which have been shown achievable without active feedback manipulation of the MHD modes. The ST CTF will test the 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 CTFmore » has been prepared and utilized as part of this study. The results show high potential for a family of lower-cost CTF devices to suit a variety of fusion engineering science test missions.« less |
| Databáze: | OpenAIRE |
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