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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.
V. J. Corcoran, C. A. Campbell, P. B. Bothwell
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 727-732
Waste Management | doi.org/10.13182/FST92-A29834
Articles are hosted by Taylor and Francis Online.
Current UK strategy for decommissioning stainless steel plant used for tritium containment centres on heating/melting the bulk metal to effect release of dissolved gases. However, hydrogen isotope containment vessels used for approximately 20 years with mercury pumps and exposed to air and water impurities, exhibit tritium burdens greatly exceeding those predicted by simple gas solution in the parent metal. Investigation into the location of, and activity release from, the vessel material indicate the existence of two major tritium sinks:- (i) the bulk metal where in-depth contamination arises from diffusion/solution; and (ii) a highly active surface layer, responsible for holding the main tritium inventory. The relatively rapid release of tritium from the surface layer at room temperature, particularly under moist conditions demands that this latter activity must be removed before plant dismantling and heating/melting is effected. Against this requirement, laboratory work has been performed to evaluate methods of effectively decontaminating stainless steel plant items by gas purge and heat treatment and also to confirm theoretical diffusion/solution calculations as an acceptable baseline for estimating gas solution in the bulk metal. This work reports the effect of wet outgassing primary containments and the effect of heating/melting on tritium burdens in stainless steel.