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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.
Kapulla, Hans Kraemer, Reinhard Heine, Rolf
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 412-418
Safety; Measurement and Accountability; Operation and Maintenance; Application | doi.org/10.13182/FST92-A29780
Articles are hosted by Taylor and Francis Online.
In the past calorimetry has been developed as a powerful tool in radiometrology. Calorimetric methods have been applied for the determination of activities, half lives and mean energies released during the desintegration of radioactive isotopes. The fundamental factors and relations which determine the power output of radioactive samples are presented and some basic calorimeter principles are discussed. At the Kernforschungszentrum Karlsruhe (KfK) a family of 3 calorimeters has been developed to measure the energy release from radioactive waste products arising from reprocessing operations. With these calorimeters, radioactive samples with sizes from a few cm3 to 2·105 cm3 and heat ratings ranging from a few mW to kW can be measured. After modifications of its inner part the most sensitive calorimeter among the three calorimeters mentioned above would be best suited for measuring the tritium inventory in T-getters of the Amersham-type. Its new time constant and sensitivity is calculated with FE-methods.