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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.
H. Y. Khater, M. E. Sawan
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2112-2116
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30032
Articles are hosted by Taylor and Francis Online.
Activation analysis has been performed for the D-3He fueled reactor ARIES-III. The activity, decay heat and biological hazard potential (BHP) have been calculated for the low activation steel (modified HT-9) first wall and shield as a function of time following the reactor shutdown. The total activity produced in the reactor at shutdown is 1549 MCi. The total activity produced in the reactor organic coolant following 30 full power years of operation without reprocessing is 458 Ci. The modified HT-9 shield qualifies for shallow land burial as Class A low level waste. The biological dose rate after shutdown at the back of the outboard shield is too high to allow hands-on maintenance. Burning all the tritium in the plasma chamber results in increasing the radioactivity generated in ARIES-III by 65% to 85% at different times following the reactor shutdown.
