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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. Kanazawa, M. Nishikawa, H. Yamasaki, K. Katayama, H. Kashimura, T. Hanada, S. Fukada
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1167-1170
Blanket and Breeder Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12623
Articles are hosted by Taylor and Francis Online.
The present authors have developed the tritium release model to represent the tritium release behavior from solid breeder materials (Li2ZrO3, Li2TiO3, Li4SiO4, LiAlO2 and Li2O). It has been found that water is released from solid breeder materials into the purge gas due to desorption of physically and chemically adsorbed water and water generation reaction and that this water affects the tritium release behavior. In this study, the amount of adsorbed water and its desorption rate for Li2ZrO3 were quantified. It was found in this experiment that Li2ZrO3 has the largest adsorption amount among the solid breeder candidates. It was also observed that Li2ZrO3 has the largest water generation capacity among the solid breeder candidates. A unique reaction at around 550°C which made up approximately 80% of the capacity of water generation was also observed. It is considered that the phase change of ZrO2 at around 550°C supplies oxygen to promote water generation reaction. Tritium release behavior from Li2ZrO3 blanket was estimated using the properties obtained in this study under the operational condition of ITER or a commercial reactor.