This paper is devoted to evaluation of activity of the IVG.1M reactor coolant and estimation of the fission products (FP) yield from the fuel rods of experimental water-cooled technological channels with low enriched uranium (WCTC-LEU) using a sampling gamma spectrometric method. The article presents the results of studies of two experimental WCTC-LEU to determine the yield of FP into the coolant of the IVG.1M reactor using a sampling gamma spectrometric method. A comparative analysis of changes in the FP yield from both experimental WCTC-LEU and regular WCTC is presented in the considered range of energy release in the reactor up to 630 MW·hour. Research results show that the FP yield remains unchanged within fluctuations when conducting more than 30 reactor experiments. The paper shows that the FPyield from the experimental WCTC-LEU averaged over all registered FPs to R/B = 5·10−7 can be considered acceptable compared to the calculated yield for sealed fuel rods R / B = 7·10−7.