Nondestructive Measurement of the Coating Thickness in the Simulated TRISO-Coated Fuel Particle for the HTGR
Description
TRISO(tri-isotropic)-coated fuel particle technology is utilized owing to its higher stability at a high temperature and its efficient retention capability for fission products in the HTGR(high temperature gas cooled reactor). The typical spherical TRISO fuel particle with a diameter of about 1 mm is composed of a nuclear fuel kernel and outer coating layers. The coating layers consist of a buffer PyC(pyrolytic carbon) layer, inner PyC(I-PyC) layer, SiC layer, and outer PyC(OPyC) layer. The thickness of the coating layer can be nondestructively measured by the X-ray radiography without generating the radioactive wastes. In this study, digital image processing technology as well as micro X-ray radiography technology was developed to measure the coating thickness for a simulated TRISO-coated fuel particle with a ZrO2 kernel instead of a UO2 kernel. At first, the coating thickness was measured by manually observing the coating layer on the radiographic image. Then, the coating thickness was measured by automatically recognizing the coating layer on the radiographic image. The coating thickness could be measured more effectively by the automatic recognition method. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- INIS-ZA--23M0016
Conference
- Title
- 3. International Topical Meeting on High Temperature Reactor Technology
- Dates
- 1-5 Oct 2006
- Place
- Johannesburg (South Africa)
INIS
- Country of Publication
- South Africa
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54072031
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COATED FUEL PARTICLES; FEDERAL REPUBLIC OF GERMANY; FISSION PRODUCTS; FORSCHUNGSZENTRUM JUELICH; HTGR TYPE REACTORS; NUCLEAR FUELS; PYROLYTIC CARBON; RADIOACTIVE WASTES; SILICON CARBIDES; SIMULATION; STABILITY; URANIUM DIOXIDE; X-RAY RADIOGRAPHY; ZIRCONIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CARBIDES; CARBON; CARBON COMPOUNDS; CHALCOGENIDES; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; EUROPE; FUEL PARTICLES; FUELS; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; INDUSTRIAL RADIOGRAPHY; ISOTOPES; MATERIALS; MATERIALS TESTING; NATIONAL ORGANIZATIONS; NONDESTRUCTIVE TESTING; NONMETALS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; TESTING; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WASTES; WESTERN EUROPE; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- Document from Juelich Preservation Project; 15 refs., 3 tabs., 15 figs.