公开(公告)号：US09927420B2

公开(公告)日：2018-03-27

申请号：US15336996

申请日：2016-10-28

Applicant: KEPCO NUCLEAR FUEL CO., LTD.

Inventor： Youngmoon Bae ,  Seungchul Yang ,  Byungkuk Lee ,  Dongyong Kwak ,  Hyunkwang Cho ,  Sunghoi Gu ,  Euijun Hwang

IPC: G01J3/427 ,  G01N33/22 ,  G01N9/24 ,  G01N21/31 ,  G21C17/06 ,  G21C3/26 ,  G01N33/00 ,  G21C3/04

CPC classification number: G01N33/222 ,  G01N9/24 ,  G01N21/25 ,  G01N21/31 ,  G01N2033/0091 ,  G01N2033/0093 ,  G21C3/26 ,  G21C3/623 ,  G21C17/06 ,  G21C19/46 ,  G21C21/02 ,  G21C2003/045

Abstract: Disclosed is a method of predicting, calculating, or analyzing the sintered density of uranium oxide (UOx) before uranium oxide is added in the pelletizing process during a process of manufacturing nuclear fuel, the method including measuring the chromaticity of ammonium diuranate using a spectrophotometer. The present invention provides a simple and highly reliable method of predicting the sintered density of uranium oxide (UOx), which overcomes the problem with a conventional technology where the sintered density of uranium oxide (UOx) can be analyzed only in a pellet state and a subsequent treatment process needs to be performed according to the analysis result.