Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method
|Publication Date:||1 January 2017|
|ICS Code (Fissile materials and nuclear fuel technology):||27.120.30|
|ICS Code (Radiation measurements):||17.240|
This document describes a method for determining the Oxygen-to-Metal (O/M) ratio in mixed uraniumplutonium oxide (U,Pu)O2 ± X pellets. The parameters given in the following paragraphs are relevant for pellets within a range of O/M ratio corresponding to 1,98 to 2,01. The method described in the document is adapted, with regard to the parameters, if the expected values of O/M ratio are outside the range.