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.2010.05.006Additional 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)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42013359
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CRACKS; DEFORMATION; FUEL PELLETS; GROUND TRUTH MEASUREMENTS; IMAGES; INDUSTRIAL RADIOGRAPHY; MELTING; POWER REACTORS; RADIATION EFFECTS; RESEARCH REACTORS; SPENT FUELS; VOIDS
- Descriptors DEC
- ENERGY SOURCES; FUELS; MATERIALS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NUCLEAR FUELS; PELLETS; PHASE TRANSFORMATIONS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TESTING
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.