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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.
Jeffery F. Latkowski, Javier Sanz, Jasmina L. Vujic, Michael T. Tobin
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1475-1479
Safety and Environment | doi.org/10.13182/FST96-A11963157
Articles are hosted by Taylor and Francis Online.
The majority of radionuclide generation/depletion codes consider only neutron reactions and assume that charged particles, which may be generated in these reactions, deposit their energy locally without undergoing further nuclear interactions. Neglect of sequential charged-particle (x,n) reactions can lead to a large underestimation in the inventories of radionuclides that make a significant impact upon various radiological indices.1 We have adopted the PCROSS code for use with the ACAB activation code to enable calculation of the effects of (x,n) reactions upon radionuclide inventories and inventory-related indices.2,3 The present work builds upon our previous work and the work completed by R. A. Forrest for magnetic fusion energy devices.4,5 Using this capability we have performed activation calculations for Flibe (2LiF + BeF2) coolant in the HYLIFE-II inertial fusion energy (IFE) power plant design. For pure Flibe coolant, we find that (x,n) reactions dominate the residual contact dose rate at times of interest for maintenance and decommissioning. For impure Flibe, however, radionuclides produced directly in neutron reactions dominate the contact dose rate, and (x,n) reactions do not make a significant contribution. Our results demonstrate the potential importance of (x,n) reactions and that the relative importance of (x,n) reactions varies strongly with the composition of the material considered. Future activation studies should include (x,n) reactions in all calculations until a method for screening their importance in a particular situation has been established.