Digital image interpretation on irradiated U3Si2/Al density 4.8 gU/cm3 using image enhancement process

Digital x-ray radiography is one of the non-destructive testing methods as part of the nuclear fuel performance evaluation process. Image interpretation is performed on the radiographic test to deliver data that can be used as a basis for evaluating nuclear fuel performance after the irradiation pro...

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Veröffentlicht in:AIP Conference Proceedings 2024-02, Vol.2967 (1)
Hauptverfasser: Artika, Refa, Sigit, Rohmad, Rahmatullah, Helmi Fauzi, Purwanta, Purwanta, Basiran, Basiran
Format: Artikel
Sprache:eng
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Zusammenfassung:Digital x-ray radiography is one of the non-destructive testing methods as part of the nuclear fuel performance evaluation process. Image interpretation is performed on the radiographic test to deliver data that can be used as a basis for evaluating nuclear fuel performance after the irradiation process. Digital x-ray radiography produces digital images with low resolution so therefore image enhancement or image quality improvement is required to simplify the interpretation process. The interpretation process is carried out on digital image of U3Si2/Al density 4.8 gU/cm3 post irradiation with burn-up variations 20%, 40%, and 60% by performing image enhancement using the ImageJ program including contrast alignment, edge enhancement, gray value histogram processing and color adjustments. Interpretation is done according the information that must be achieved from digital x-ray radiography tests of U3Si2/Al density 4.8 gU/cm3 post irradiation which is also a basic reference in the image enhancement process. This information for instance are uranium homogeneity, consistency of meat-cladding dimensions, mapping of cladding-meat anomalies, and mapping markers from U3Si2/Al digital images with a density of 4.8 gU/cm3 post irradiation with burn-up variations 20%, 40%, and 60%. The interpretation results can be used as a reference for digital x-ray radiography tests to represent the evaluation of nuclear fuels performance after irradiation process with different burn-up values.
ISSN:0094-243X
1551-7616
DOI:10.1063/5.0193139