Non-Destructive Assay of 235U and 239Pu Using a Lead Slowing-Down Spectrometer

摘要

The use of a Lead Slowing-Down Spectrometer (LSDS) is considered as a possible option for non destructive assay of fissile material in used (spent) nuclear fuel. The primary objective is to quantify the remaining fissile content of the fuel consisting mainly of 239Pu and 235U. The characterization of spent fuel is particularly important for nuclear safeguards and for determining the fuel burn-up level in view of reprocessing and recycling of used fuel. The LSDS is well suited for spent fuel testing due to its ability to assay non-destructively and directly. Several studies discussed the potential of the LSDS for spent fuel assay1'2'3'4. In addition, LSDS systems have been successfully used by INTERATOM and the Research Center in Karlsruhe, Germany, as well as by Rensselaer Polytechnic Institute (RPI) to assay fresh fuelpins1'2'3'4'5.