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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
G. H. Miley, H. Hora, B. Malekynia, M. Ghoranneviss
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 384-390
IFE Target Design | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8931
Articles are hosted by Taylor and Francis Online.
Block ignition was proposed recently as a possible alternate approach to fast ignition for ICF fusion. This approach uses a modified petawatt-picosecond (PW-ps) laser pulse shape where the prepulse is strongly suppressed. This results in highly directed plasma blocks due to nonlinear (ponderomotive) force acceleration with space charge neutral ion current densities above 1011 Amp/cm2. This allows ignition of deuterium-tritium targets at densities somewhat above solid state density. However, a key issue has been the need to reduce the extremely high thresholds for the high energy flux densities of the blocks as pointed out in a related theory by Bobin and Chu in 1972. Here we show how the threshold can be reduced by a factor up to 20 by two effects. An important contribution comes from the inhibition factor for thermal conductivity due to electric double layers created in the block process. The second effect is the reduction to the stopping length, giving increased heating by the fusion product alpha due to collective interactions in the blocks. Results from including these effects in a hydrodynamic analysis are presented. The advantage of this approach for an ICF fusion reactor is the relaxed pre-compression requirement for high gain.