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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.
Vijay R. Nargundkar, Tejen Kumar Basu, Om Prakash Joneja
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 354-359
Technical Paper | Blanket Engineering | doi.org/10.13182/FST88-A20267
Articles are hosted by Taylor and Francis Online.
The measurement of 14-MeV neutron multiplication is given for a 4-cm-thick thoria assembly in rectangular geometry. This agrees within 2% of the corresponding calculated value of neutron multiplication obtained by using the general geometry Monte Carlo code MORSE-E and the Los Alamos National Laboratory 30-group neutron cross-section set Claw-IV in P3 scattering approximation. The results confirm Kushneriuk and Wong's calculational analysis of the Shief et al. experiment with a large cylindrical thorium metal assembly using the ENDF/B-IV library, as well as Kobayashi et al. 's differential neutron spectrum measurements in a spherical thoria pile and thorium metal slab by the time-of-flight method.
