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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.
R. Wölfle, A. Suhaimi, S. M. Qaim
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 71-75
Technical Notes | doi.org/10.13182/NSE93-A35524
Articles are hosted by Taylor and Francis Online.
Beryllium samples together with sets of 12 flux monitor foils having different reaction thresholds were irradiated in six different d(Be) neutron fields (Ed = 17.5 to 30.0 MeV). The shapes of the neutron spectra were determined by using the SAND-II iterative unfolding code. In a second calculational step, the excitation function for the (n,xt) process on 9 Be was obtained from the neutron flux distributions and the measured tritium activities in beryllium samples. For this purpose, the SAND-II code as well as a generalized least-squares unfolding code were applied, and both gave similar results. The excitation function thus obtained is in excellent agreement with the values obtained by using monoenergetic neutrons in the region of 13 to 20 MeV.