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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.
Dongxun Zhang, Wei Liu, Yuan Qian, Ji Que
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 681-684
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T109
Articles are hosted by Taylor and Francis Online.
Tritium was generated by the interaction of neutrons with the lithium and beryllium in the molten salt reactors (MSRs), which use Flibe as one of solvents of fluoride fuel. Tritium as by-product in the MSRs would be an important safety issue because it could easily diffuse through high temperature heat exchangers into environment. The experimental technique of gas driven permeation was used to investigate the transport parameter of hydrogen in Hastelloy C-276 which was considered as one of the candidate structure materials. The measurements were carried out at the temperature range of 400-800°C with hydrogen loading pressures ranging from 5×103 to 4×104 Pa. The H diffusive transport parameters for Hastelloy C-276 followed an Arrhenius law in this temperature range and were decreased due to the existence of the alloying elements compared with Ni201. The possible reason may be the trapping effects, which were formed by the alloying elements of Mo and Cr in the matrix. At the same time, the thin oxidation layer formed by the high Cr content could lead to the slower dissociation process of H2 at the surface.