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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.
Ezio Bittoni, Marcel Haegi
Fusion Science and Technology | Volume 18 | Number 3 | November 1990 | Pages 373-383
Alpha Particles in Fusion Research | Technical Paper | doi.org/10.13182/FST90-A29270
Articles are hosted by Taylor and Francis Online.
Calculation of alpha-particle confinement by a guiding center orbit-following numerical code requires the computation of very long particle trajectories. Due to their enormous length, these computations are subject to the possible accumulation of small errors, and the alpha-particle population is usually extrapolated from a single-particle history for every point of the initial parameter space. To overcome these difficulties, a numerical diffusion coefficient is derived for each point of the initial parameter space by averaging over a certain number of single-particle histories for each point of this space. This method has been applied to fast-alpha-particle confinement of the Next European Torus benchmark and the numerically derived diffusion coefficients are compared with analytical expressions from theoretical models.