Specifies an analytical method for the accurate and precise determination of uranium in solutions of reactor fuels fed to reprocessing plants and in the uranyl(VI) nitrate product solutions from such plants. The method can be used directly for the analysis of nitric acid solution of most uranium and uranium/plutonium oxide reactor fuels, either irradiated or unirradiated. Fission products equivalent to up to 10 % burn-up of heavy atoms do not interfere.
Текущий статус : WithdrawnДата публикации : 1983-12
Версия : 1Число страниц : 5
Технический комитет:Nuclear installations, processes and technologies