https://www.selleckchem.com/products/bay-2666605.html The problem of handling nuclear power plant irradiated structural materials holds one of the central places in the nuclear power industry. High toxic 10Be with a half-life of T1/2 = 1.6 × 106 years is discovered in NPP structural materials after reactor operating. 10Be decays through only electrons' emission. Pure beta emitters are extremely difficult to determine in irradiated structural materials and radioactive waste. We proposed a photoactivation approach for determining the 10Be activity in NPP samples. The proposed method involves determining 9Be and 10B concentrations and subsequent recalculation of 10Be activity formed in 9Be(n, γ)10Be and 10B(n, p)10Be reactions. The amount of 9Be and 10B is determined by samples' photoactivation using an electron accelerator and 9Be(γ, 2n)7Be-, 10B(γ, p2n)7Be-reactions. These reactions' experimental yields were measured for 20, 40, and 55 MeV boundary energies of the bremsstrahlung beam. The proposed technique was tested on samples of ChNPP 2nd unit irradiated structural materials. The technique's calculated error is about 15-20%; the sensitivity is 1 Bq × g-1.Inspired by microbial diagenesis and mounding, microbial mineralization technology has been widely used in the treatment of heavy metal and radionuclide contamination. S. pasteurii can decompose urea as a source of energy to produce CO32- in the microbial mineralization system. Therefore, strontium-contaminated radioactive wastewater can be effectively treated by combining CO32- with surrounding strontium ions (Sr2+) to form strontium carbonate (SrCO3). Herein, we investigated how the concentration of graphene oxide (GO) and mineralization time influence the morphology of SrCO3 and the mineralization efficiency. GO was used as a crystal regulator to solidify the radionuclide strontium in the microbial mineralization system to obtain large-scale rock-like SrCO3 minerals. The results showed that GO can adsorb the su