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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
J.M. Perlado, J. Sanz,a D. Guerra, A.S. Perez
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 709-715
Inertial Fusion | doi.org/10.13182/FST91-A29428
Articles are hosted by Taylor and Francis Online.
The feasibility of the ferritic alloy HT-9 as the main component of the first structural wall (FSW) of inertial confinement fusion (ICF) reactors, such as HIBALL-II or LIBRA, which use thin film liquid protection through porous tubes (INPORT) has been studied in terms of radiation damage and activation. Swelling and shift in the ductile brittle transition temperature (DBTT) have been analyzed in the light of the results of experimental fast breeder reactors, which are demonstrated to be good experimental tools in our ICF range. The good performance of HT-9 is remarkable. An analysis of the generation of new solid transmutants and the depletion of initial constituents is given. Activation has been studied using recycling and shallow land burial (SLB) criteria. The interest has been focussed in a reduced activation HT-9 (Niobium-free). Recycling using HT-9 is shown to be not feasible. SLB waste disposal is also not feasible. The critical role of some short lived isotopes as Pt193, Nb93m, Re186 is analyzed, together with that of the more conventional Re186m, Nb94, Bi210m.
