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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.
T. Kunugi, M. Z. Hasan
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1024-1029
Blanket Technology | doi.org/10.13182/FST91-A29477
Articles are hosted by Taylor and Francis Online.
Convective heat transfer in the thermally developing region in a circular channel of the first wall and limiter/divertor plates of a fusion reactor has been analyzed numerically. The surface heat flux on a coolant channel in these plasma facing components varies circumferentially. The flow is assumed non-MHD fully-developed laminar and turbulent in a circular tube. The nonuniformity of surface heat flux greatly affect the Nusselt number and thermal entry length. For the cosine distribution of surface heat flux, the steady-state Nusselt number can be reduced at the point of maximum heat flux by as much as 38%, 62% and 37% for fully-developed laminar Poiseuille, laminar slug and turbulent flows, respectively. Thermal entry length can be increased by up to 2.4 times for laminar flow and 3.5 times for turbulent flow due to the nonuniformity of surface heat flux. If this reduction of Nusselt number due to the nonuniformity of surface heat flux is disregarded, the film temperature drop in the coolant channels of plasma facing components of a fusion reactor will be underestimated by 37% to 62%. This will result in an underestimation of the maximum structure temperature. The increase in entry length is not likely to affect the thermal-hydraulic design of a conventional divertor plate.