We examine the potential fuel cycle performance of high assay low-enriched uranium fueled small light water reactors by considering several floating small reactor concepts of Russian origin with 235U enrichment at 10%, 15%, and 19.7%. These enrichments are generic but representative of the reactor concepts being considered. The small reactor concepts were considered parametrically at two different power densities and neutron leakage fractions. The analysis was performed for the U.S. Department of Energy Office of Nuclear Energy using the evaluation metrics from the Evaluation and Screening (E&S) Study. The reference reactor system in a once-through fuel cycle with an enrichment greater than 5%, but less than 20%, in the E&S study is a graphite-moderated modular high temperature gas-cooled reactor (mHTGR). The neutron spectrum of an mHTGR is very different from these Russian floating small reactor concepts, which is why this analysis was conducted.The fuel cycle analysis indicates that increasing core leakage negatively impacts the natural resource requirements as well as the spent nuclear fuel and high-level waste radioactivity normalized to a giga-watt electric year (GWe-yr) basis. Further, we found that the 235U enrichment of the fuel and the rated core power density have limited fuel cycle performance impacts. One impact is the slightly higher discharge burnup of the de-rated power cases resulting in different spent nuclear fuel and high-level waste radioactivity at 100 and 100,000 years after fuel discharge. The most significant result from the study is the observation that all the enrichment and power density cases resulted in decreased radioactivity at 100,000 years relative to the reference mHTGR example case with 15.5%-enrichment from the E&S study.