Bachman & LaPointe, P.C.
Method for measuring lanthanide content dissolved in uranium oxide
The present invention relates to a method for measuring the content of Lanthanides dissolved in uranium oxide, wherein the Lanthanides content in the nuclear fuel pellet is measured using the thermo gravimetric analysis which measures the weight variation caused by the oxidation and heat treatment of the nuclear fuel pellet. This method provides an advantage in that the Lanthanide content can be measured using relatively simple equipments such as an electric furnace and a balance.
Korea Hydro & Nuclear Power Co., Ltd. Korea Atomic Energy Research Institute
C C C G C
C01G C01P C01G G01N C01P
inventional additional inventional inventional additional
Kun-Woo Keon-Sik Ki-Won Youn-Ho Jae-Ho
Song Kim Kang Jung Yang