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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.
I. N. Sviatoslavsky, A. R. Raffray, M. E. Sawan, X. Wang
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 535-539
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | doi.org/10.13182/FST05-A739
Articles are hosted by Taylor and Francis Online.
A multi-institutional study HAPL (High Average Power Laser) is investigating a relatively near term conceptual design of a laser driven inertial confinement reactor. A primary focus of the study is the protection of the first wall (FW) from the target emanations. This paper gives a brief analysis of one of several possible blankets that can be integrated with the chosen FW protection scheme. The structural material is conventional ferritic steel (FS) F82H cooled with liquid lithium. The maximum average temperature is constrained to 550°C. The chamber radius is 6.5 m at midplane, tapering to 2.5 m at the ends, and is surrounded by a cylindrical vacuum vessel. The first wall (FW) is 0.35 cm FS, which has a 0.1 cm thick layer of tungsten bonded to it facing the target. The FW is cooled with Li admitted at the bottom of the blanket, flows through a gap between 0.25-0.5 cm to the top, then returns through the center of the blanket channel to the bottom. There are 60 laser beam ports situated around the chamber. The tritium breeding ratio (TBR) is 1.124. A Brayton cycle is envisaged with an efficiency in the range of 42-44%.