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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
M. A. Porracchia, M. M. Reocreux, M. C. Rousseau
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 375-379
Technical Paper | doi.org/10.13182/NSE88-A23569
Articles are hosted by Taylor and Francis Online.
During the past few years, there has been an increasing effort to understand the behavior of nuclear power plants (NPPs) in normal and abnormal situations. To achieve this goal, large computer codes that allow the description of two-phase flows with sources and sinks of mass and heat have been built in many countries. The analysis of NPP situations often requires a large computation time, so efficient calculational methods are needed to minimize the cost of these studies. Thermal-hydraulic models and calculational methods used in the codes are reviewed. Computational methods and solution procedures involved in some European operating and safety codes are described. Developments concerning code optimization and adaptation of numerical methods to the new supercomputer architectures are discussed.