Method of measuring radioactive material of ingot using NaI gamma scintillator

摘要

Disclosed is a method of measuring radioactive material of an ingot, in which an ingot having a volume produced by subjecting metal waste generated in nuclear fuel processing or production facilities to melting decontamination undergoes gamma spectroscopy using a NaI detector to measure gamma rays of U-235 (185.72 keV, 57.2%) among uranium isotopes, followed by performing detector calibration using a certified reference material and self-absorption correction depending on the density of a medium using MCNP computer code, and which enables rapid determination of whether the ingot subjected to melting decontamination may be self-disposed of or not.