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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.
J. J. MacFarlane, P. Wang, G. A. Moses
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 703-708
Inertial Fusion | doi.org/10.13182/FST91-A29427
Articles are hosted by Taylor and Francis Online.
We present results from radiation transport calculations for plasma conditions that are expected for the buffer gases of high-gain inertial confinement fusion (ICF) target chambers. In our calculations, the plasmas are not assumed to be in local thermodynamic equilibrium (LTE). The state of the plasmas is obtained by solving multilevel atomic rate equations self-consistently with the radiation field. Radiation is transported using an escape probability model. Atomic physics data is generated using a combination of Hartree-Fock, distorted wave, and semi-classical impact parameter models. Our results show that the self-attenuation of line radiation results in a significant reduction in the radiation flux at the target chamber first wall. We compare our results with those from other calculations and find that the heat fluxes at the first wall are significantly lower than previously predicted by multigroup radiation diffusion models. The lower heat fluxes suggest that thermal conduction within the first wall can act to keep temperatures near the surface of the wall much lower than previously thought, thus reducing problems associated with thermal stresses and vaporization. We discuss the ramifications of our results for the SIRIUS-T ICF reactor.