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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.
A. W. Molvik, R. W. Moir, D. D. Ryutov, T. C. Simonen
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 70-76
Fusion | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13399
Articles are hosted by Taylor and Francis Online.
Axisymmetric mirrors can be MHD-stabilized by end losses. Neutral-beam-sustained operation to ~0.6, and Te~0.2 keV, with 5 ms 5 MW neutral beams on the Gas Dynamic Trap (GDT) has been demonstrated at the Budker Institute in Novosibirsk, Russia. Applications of this concept can reduce risks in the fusion program. A GDT-scale facility could test plasma-material interactions (PMI) at up to 400 MW/m2 and 5 s pulse duration for divertor development. Extrapolation of the GDT to a Dynamic Trap Neutron Source, DTNS, provides a DT-fusion neutron flux of 2 MW/m2 over 1 m2, at a power-plant efficiency of Q ~ 0.07. (A DTNS enables development and testing of materials and sub-component structures, for fusion power plants, MFE or IFE. A DTNS functions regardless of whether the tested components work. These developments would reduce risks for a tokamak Fusion Nuclear Science Facility (FNSF)). Further extrapolation to 0.2 Q 10 single-cell or tandem mirror yields several fusion-fission hybrid applications. Further extension to a pure-fusion axisymmetric-tandem-mirror power plant, requires Q>10. Tandem mirrors demand the use of different stabilization techniques that are not dependent on out-flowing plasma, a number of which have been proposed, and could be experimentally tested on the GDT.