Processing of the Msre Flush and Fuel Salts.

Review of Hazards Associated with Molten Salt Reactor Fuel Processing Operations

“…The uranium was replaced by a smaller amount of nearly pure 233 U to provide equivalent reactivity. The facilities and procedures that were used to accomplish the uranium removal and fuel salt purification (oxide removal) are described in ORNL-TM-2578, 9 which is the basis for the information in the following discussion.…”

Efficient Isotope Recovery and Seamless Recycle of Target Material in a Salt Matrix

“…It was apparent from our initial survey that attractive processing options could be identified for 232 U production and might be present for 99 Mo production. For the case of 232 U production, halide volatility is the most attractive flowsheet and there is little need to elaborate further because it parallels (but can be simpler than) the recovery of 235 U from the Molten Salt Reactor Experiment (MSRE) (15), (16). For the case of 99 Mo recovery, the chemistry of near-noble and noble fission products, as well as their precursors in molten halides, is not well understood, but what is known (17), (18), (19), (20), 21, (22) provides some hope for pursuing online isolation of the noble metals (including Mo).…”

Batch-Scale Hydrofluorination of Li27BeF4 to Support Molten Salt Reactor Development

“…Fluorine was capable of oxidizing the salt so dramatically that not only did it fluorinate oxygenic impurities but also fluorinated dissolved uranium tetrafluoride to volatile uranium hexafluoride, which bubbled out of the salt. The redox potential imposed by a pure fluorine sparge was found to cause extensive corrosion to the purification vessel [10][11][12].…”