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Homepage>BS Standards>27 ENERGY AND HEAT TRANSFER ENGINEERING>27.120 Nuclear energy engineering>27.120.30 Fissile materials>BS EN ISO 16793:2021 Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination
immediate downloadReleased: 2021-02-22
BS EN ISO 16793:2021 Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination

BS EN ISO 16793:2021

Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination

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Standard number:BS EN ISO 16793:2021
Pages:16
Released:2021-02-22
ISBN:978 0 539 14660 8
Status:Standard
DESCRIPTION

BS EN ISO 16793:2021


This standard BS EN ISO 16793:2021 Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination is classified in these ICS categories:
  • 27.120.30 Fissile materials and nuclear fuel technology

This document describes the ceramographic preparation of uranium dioxide (UO2) sintered pellets for qualitative and quantitative microstructure examinations.

These examinations can be carried out before and after thermal or chemical etching.

They enable

  • observations of fissures, inter- or intra-granular pores and inclusions, and

  • measurement of pore and grain size and measurement of pore and grain size distributions.

The measurement of average grain size can be carried out using a classical counting method as described in ISO 2624 or ASTM E112[3], 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 grain-size 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.