Published October 2010 | Version v1
Journal article

Defect sizing of post-irradiated nuclear fuels using grayscale thresholding in their radiographic images

  • 1. Department of Physics and Applied Mathematics, Pakistan Institute of Engineering and Applied Sciences, P.O. Nilore, Islamabad 45650 (Pakistan)
  • 2. Nuclear Engineering Division, Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad 45650 (Pakistan)
  • 3. Nondestructive Testing Group, Directorate of Technology, Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad 45650 (Pakistan)

Description

Quantification of different types of material defects in a number of reference standard post-irradiated nuclear fuel image samples have been carried out by virtue of developing a computer program that takes radiographic images of the fuel as input. The program is based on user adjustable grayscale thresholding in the regime of image segmentation whereby it selects and counts the pixels having graylevel values less than or equal to the computed threshold. It can size the defects due to chipping in nuclear fuel, cracks, voids, melting, deformation, inclusion of foreign materials, heavy isotope accumulation, non-uniformity, etc. The classes of fuel range from those of research and power reactors to fast breeders and from pellets to annular and vibro-compacted fuel. The program has been validated against ground truth realities of some locally fabricated metallic plates having drilled holes of known sizes simulated as defects in them in which the results indicate that it either correctly selects and quantifies at least 94% of the actual required regions of interest in a given image or it gives less than 8.1% false alarm rate. Also, the developed program is independent of image size.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.05.006

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.05.006;
PII
S0029-5493(10)00324-9;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
10
Journal Page Range
p. 3455-3461
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
4. international topical meeting on high temperature reactor technology
Acronym
HTR 2008
Dates
28 Sep - 1 Oct 2008
Place
Washington, DC (United States)

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.