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CEN - EN ISO 21484

Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method

active, Most Current
Organization: CEN
Publication Date: 1 June 2019
Status: active
Page Count: 14
ICS Code (Fissile materials and nuclear fuel technology): 27.120.30
ICS Code (Radiation measurements): 17.240
scope:

This document describes a method for determining the Oxygen-to-Metal (O/M) ratio in mixed uranium-plutonium 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.

 

Document History

EN ISO 21484
June 1, 2019
Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method
This document describes a method for determining the Oxygen-to-Metal (O/M) ratio in mixed uranium-plutonium oxide (U,Pu)O2 ± X pellets. The parameters given in the following paragraphs are relevant...

References

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