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UKAEA-CCFE-PR(24)2592023
Two-micron thick erbium oxide tritium barrier coatings have been prepared by aerosol injection chemical vapor deposition and subsequently irradiated with 33 MeV Au 6+ ions at fluences up to 2.1×10 15 Au/m 2 at 550 o C. Scanning electron microscopy, X-ray diffraction and transmission electron microscopy were used to investigate the coating surf…
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UKAEA-CCFE-PR(23)1482023
Silicon carbide fibre–reinforced silicon carbide matrix (SiCf/SiC) composites are desirable in structural nuclear applications due to their low density, high temperature strength and tolerance to energetic radiation. We have subjected two industrial grades of SiCf/SiC to high energy He²⁺ ion irradiation, up to 10,000 a…
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UKAEA-CCFE-PR(24)2442022
Zirconium alloys are widely used as the fuel cladding material in pressurised water reactors where a significant population of defects and dislocations is produced by exposure to neutrons. We present and interpret synchrotron microbeam X-ray diffraction measurements of proton- irradiated Zircaloy-4, where we identify a transient peak and the sub…
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UKAEA-CCFE-PR(22)252022
Hydride precipitation and reorientation has the potential to embrittle zirconium alloys. This study aims to better understand the influence of the Zr microstructure on hydride precipitation and reorientation. Specifically, the crystallography, phase stability and morphology of hydride precipitation was correlated to microstructural variations due t…
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