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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. Abdou, E. L. Vold, C. Y. Gung, M. Z. Youssef, K. Shin
Fusion Science and Technology | Volume 9 | Number 2 | March 1986 | Pages 250-285
Technical Paper | Tritium System | doi.org/10.13182/FST86-A24715
Articles are hosted by Taylor and Francis Online.
Conditions necessary to achieve deuterium-tritium fuel self-sufficiency in fusion reactors are derived through extensive modeling and calculations of the required and achievable tritium breeding ratios as functions of the many reactor parameters and candidate design concepts. It is found that the excess margin in the breeding potential is not sufficient to cover all present uncertainties. Thus, the goal of attaining fuel self-sufficiency significantly restricts the allowable parameter space and design concepts. For example, the required breeding ratio can be reduced by (a) attaining high tritium fractional burnup, >5%, in the plasma, (b) achieving very high reliability, >99%, and very short times, <1 day, to fix failures in the tritium processing system, and (c) ensuring that nonradioactive decay losses from all subsystems are extremely low, e.g., <0.1 % for the plasma exhaust processing system. The uncertainties due to nuclear data and calculational methods are found to be significant, but they are substantially smaller than those due to uncertainties in system definition.