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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.
D.A. O'Brien, D. Steiner
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 809-814
Safety and Environment — I | doi.org/10.13182/FST89-A39794
Articles are hosted by Taylor and Francis Online.
This paper presents a probabilistic approach for mechanical design problems and applies this approach to a fusion reactor first wall design analysis. The method developed is based on Response Surface Methods, developing an approximation to a consequence of interest. A probability distribution for the consequence is found by Monte Carlo sampling of the input parameters probability distribution and then using the response surface. Adopting a defined criteria for failure, a probability of the consequence exceeding the criteria is found. In this paper the method is applied to the examination of neutron wall load implications. The motivation for this work is to provide an additional tool for design development and assessment.