Development of a Small Liquid Sodium Purification Loop
Generation IV nuclear reactors provide management solutions to address spent fuel problems. The most researched Generation IV reactor is the sodium cooled fast reactor (SFR). Improved engineering is has allowed for systematic improvements in both the safety and efficiency of power production. However, before a SFR can be brought back online in the Untied States, constructive research must be pursued on numerous scales to ensure the capabilities of aforementioned reactors. While larger research facilities such as the one at Argonne National Laboratory or the University of Wisconsin - Madison address some of the larger scale studies surrounding the SFR, Fort Lewis College (FLC) is aiming to provide small scale studies on liquid sodium as a thermal hydraulic cooling system. The sodium diagnostic loop at FLC is constructed to conduct research that includes: analyzing pumping characteristics, thermal stratification, freeze plug analysis, and corrosion studies. The FLC loop is attached to an inert glovebox so these experiments can be conducted with an additional layer of safety. The objective of this sodium research apparatus is to combine the best features of each instrument commonly associated with sodium research loops in a cost effective manner while still obtaining high fidelity data. Furthermore, an innovative design of the loop maximizes the volume of available research space inside of the glovebox by mounting the diagnostic loop adjacent to the glovebox.