NEN-ISO 16793
Nuclear fuel technology - Guide for ceramographic preparation of UO₂ sintered pellets for microstructure examination
| Organization: | NEN |
| Publication Date: | 1 March 2005 |
| Status: | active |
| Page Count: | 14 |
| ICS Code (Fissile materials and nuclear fuel technology): | 27.120.30 |
scope:
This International Standard describes the ceramographic preparation of uranium dioxide (UO2) sintered pellets for qualitative and quantitative microstructure examinations. These examinations may be carried out before and after thermal or chemical etching. They enable - observations of fissures, inter- or intra-granular pores and inclusions, - measurement of pore and grain size and measurement of pore and grain size distributions. The measurement of average grain size may be carried out using a classical counting method as described in ISO 2624 or ASTM E112, i.e. intercept procedure, comparison with standard grids or reference photographs. The measurement of pore-size distributions is usually carried out by an automatic image analyser. If the grainsize distributions are also measured with an image analyser, it is recommended that thermal etching be used to reveal the grain structure uniformly throughout the whole sample.
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