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ASTM C1868-18
Standard Practice for Ceramographic Preparation of UO2 and Mixed Oxide (U,Pu)O2 Pellets for Microstructural AnalysisMore info
1.1 This practice describes the procedure for preparing nuclear-grade uranium dioxide (UO2) or mixed uranium-plutonium dioxide (MOX or (U,Pu)O2)), sintered and non-irradiated pellets for subsequent microstructural analysis (hereafter referred to as ceramographic examination).
| Author | ASTM |
|---|---|
| Editor | ASTM |
| Document type | Standard |
| Format | File |
| ICS | 27.120.30 : Fissile materials and nuclear fuel technology |
| Number of pages | 5 |
| Set | ASTMVOL1201 |
| Year | 2018 |
| Country | USA |
| Keyword | ASTM 1868;ASTM C1868;ASTM C1868;10.1520/C1868-18 |