The objective of the present study was to provide further data on E110G cladding behaviour. The results presented here are from new post-test examinations (PTEs) carried out on samples of secondary hydriding experiments conducted earlier in MTA EK. The as-received Zr-1%Nb cladding samples were pressurised at high temperature to balloon and burst and then oxidised in steam atmosphere. The post-test investigation was focusing on geometric change in the cladding, ductility, oxidation and hydrogen absorption. Outer and inner oxide layers were formed on the samples, with increasing thickness near the thermal centre. The results include radial and axial distribution of oxygen in the cladding after oxidation. The hydrogen uptake of the alloy shows the expected characteristic axial distribution. Mechanical testing of the oxidised and non-oxidised samples confirmed the results of the previous mechanical tests that after ballooning the samples still had notable flexural strength, whereas after oxidation this decreased. The results were evaluated against those obtained through simulations, making it possible to estimate the level of oxidation, and to develop better models through further simulation.
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)