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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.
M. Kobayashi, N. Ohyabu, T. Mutoh, R. Kumazawa, Y. Feng, M. Shoji, T. Morisaki, S. Masuzaki, A. Sagara, R. Sakamoto, T. Seki, J. Miyazawa, T. Watanabe, M. Goto, K. Ideda, H. Kasahara, S. Morita, B. J. Peterson, N. Ashikawa, K. Saito, S. Sakakibara, T. Tokuzawa, Y. Nakamura, K. Narihara, I. Yamada, H. Yamada, A. Komori, O. Motojima, LHD Experimental Group
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 566-573
Technical Paper | The Technology of Fusion Energy - High Heat Flux Components | doi.org/10.13182/FST07-A1549
Articles are hosted by Taylor and Francis Online.
The divertor performance of LHD is studied for the two configurations, LID and HD. It is shown that the both divertor configurations play important roles for obtaining high performance plasmas in LHD: the large pumping capability of the LID to keep the low edge density in the IDB-SDC plasma, the large wetted area and the flexibility of strike point sweep of HD to reduce the power load on the divertor plates in long pulse operations. The possible effect of the ergodic layer on impurity retention in divertor is discussed by using the 3D edge transport modelling. It is found that the drag force exerted by the plasma flow can dominate over the thermal force, providing the impurity retention effect. The further changes needed to improve the current divertor configurations are discussed. New divertor designs for the future upgrade of LHD and for a LHD-type reactor are presented.