What is ISO 21484- O/M ratio in MOX pellets about?
ISO 21484 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 ISO 21484 is adapted, with regard to the parameters, if the expected values of the Oxygen-to-Metal ratio are outside the range.
Who is ISO 21484- O/M ratio in MOX pellets for?
ISO 21484 on determining O/M ratio in MOX pellets by the gravimetric method is relevant to:
- Nuclear power stations
- Nuclear fuel technology providers
- Fissile material manufacturers
- Military and defence authorities
- Atomic research organizations
- Regulatory bodies
Why should you use ISO 21484- O/M ratio in MOX pellets?
Mixed uranium-plutonium oxide is a type of nuclear fuel that contains more than one oxide of fissile material, typically plutonium blended with natural uranium, reprocessed uranium, or depleted uranium. MOX fuel is an alternative to the low-enriched uranium (LEU) fuel used in the majority of nuclear power reactors.
ISO 21484 provides you with the simple and accurate method for the determination O/M ratio in MOX pellets. This can help you evaluate the oxidation behaviour of materials used in nuclear fuel technology.