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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.
Douglass L. Henderson, Mohamed E. Sawan, Gregory A. Moses
Fusion Science and Technology | Volume 13 | Number 4 | May 1988 | Pages 594-615
Technical Paper | ICF Target | doi.org/10.13182/FST88-A25137
Articles are hosted by Taylor and Francis Online.
Biological dose rate calculations have been performed for a point external to the diode vacuum casing of the proposed Light Ion Fusion Target Development Facility for times following an operational period of 1 month. The primary diode material considered is Type 304LN stainless steel, with an alternative material of Al-6061-T6. Using a realistic pulse-sequence calculation scheme to account for the pulsed operation mode of the facility, it is shown that for both the stainless steel and aluminum diodes the dose rates external to the diode vacuum casing are > 1 rem/h after a 1-day shutdown period. After a 1-week shutdown period, the dose rates have dropped to 90 and 12 mrem/h, respectively.