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).
Product Details
- Published:
- 01/01/2018
- Number of Pages:
- 5
- File Size:
- 1 file , 93 KB
