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Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
M. Murakami, E.F. Jaeger, R. Majeski, C.K. Phillips, D.A. Rasmussen, J.H. Rogers, G. Schilling, J.E Stevens, G. Taylor, C.Y. Wang, J.R. Wilson, D.B. Batchelor, M.G. Bell, R.V. Budny, C.E. Bush, N.L. Bretz, D. Darrow, A.C. England, E. Fredrickson, R. Goldfinger, G. Hammett, G.R. Hanson, J.C. Hosea, H.K. Park, S.D. Scott, E. Synakowski, R.M. Wieland, J.B. Wilgen, M.C. Zarnstorff
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 131-137
Overview Paper | doi.org/10.13182/FST95-A11947057
Articles are hosted by Taylor and Francis Online.
This paper describes results of the first experiments utilizing high-power ion cyclotron range of frequency (ICRF) to heat deuterium-tritium (D-T) plasmas in reactor-relevant regimes on the Tokamak Fusion Test Reactor (TFTR). Results from these experiments have demonstrated efficient core, second harmonic, tritium heating of D-T supershot plasmas with tritium concentrations ranging from 6%-40%. Significant direct ion heating on the order of 60% of the input radio frequency (rf) power has been observed. The measured deposition profiles are in good agreement with two-dimensional modeling code predictions. Energy confinement in an rf-heated supershot is at least similar to that without rf, and possibly better in the electron channel. Efficient electron heating via mode conversion of fast waves to ion Bernstein waves (IBW) has been demonstrated in ohmic, deuterium-deuterium and DT-neutral beam injection plasmas with high concentrations of minority 3He (n3He/ne = 15% - 30%). By changing the 3He concentration or the toroidal field strength, the location of the mode-conversion radius was varied. The power deposition profile measured with rf power modulation indicated that up to 70% of the power can be deposited on electrons at an off-axis position. Preliminary results with up to 4 MW coupled into the plasma by 90-degree phased antennas showed directional propagation of the mode-converted IBW. Analysis of heat wave propagation showed no strong inward thermal pinch in off-axis heating of an ohmically-heated target plasma in TFTR.