Method of analyzing sintered density of uranium oxide (UOx) using spectrophotometer

A method of predicting a sintered density of a uranium oxide (UOx) pellet for the nuclear fuel, the method comprising:

• obtaining standard data including a sintered density of a uranium oxide (UOx) pellet with respect to a chromaticity value of ammonium diuranate powder by measuring a sample uranium oxide (UOx) pellet and sample ammonium diuranate powder, wherein the sample ammonium diuranate powder is precursor of the sample uranium oxide (UOx) pellet;
• measuring a chromaticity value of target ammonium diuranate powder in a manufacturing process of a target uranium oxide (UOx) pellet using a spectrophotometer;
• finding a corresponding chromaticity value, in the standard data, to the chromaticity value of the target ammonium diuranate powder;
• and
• predicting the sintered density of the target uranium oxide (UOx) pellet by obtaining the sintered density, from the standard data, with respect to the corresponding chromaticity value.