The effects of manufacturing uncertainties on the stresses in the TRISO-coated fuel particle
Description
Tristructural-isotropic (TRISO) coated fuel particles are key components in the high-temperature gas-cooled reactor (HTGR) fuel elements, and their integrity is potentially important for the nuclear reactor safety. Many fuel performance models were established concerning the stress calculations of TRISO particles, however, some gaps remain in what specific role the particle geometry plays in the stress calculations. Therefore, analytic solution calculations were employed in the paper to evaluate the tangential and radial particle stresses under various cases. Eleven cases were studied accounting for the different dimensions of the kernel, buffer and the IPyC/SiC/OPyC coating layers as well as the variation of PyC density and anisotropy during the manufacturing processes. Subsequently, the geometry statistics was introduced in the pressure vessel model and the PyC-involved stress model to update the calculated stresses of TRISO particles. The present work determined an important role of the particle dimension variations in the stress calculations, which potentially provided a path to the optimization of the design and manufacturing processes of TRISO particles. (author)
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Additional details
Publishing Information
- Imprint Title
- 9th International Conference on High Temperature Reactor Technology (HTR2018)
- Imprint Pagination
- vp.
- Journal Page Range
- 12 p.
- Report number
- INIS-PL--23M0001
Conference
- Title
- 9. International Conference on High Temperature Reactor Technology
- Acronym
- HTR2018
- Dates
- 8-10 Oct 2018
- Place
- Warsaw (Poland)
INIS
- Country of Publication
- Poland
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54062007
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANISOTROPY; COATED FUEL PARTICLES; DENSITY; DESIGN; FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; FUEL ELEMENTS; HTGR TYPE REACTORS; NUCLEAR FUELS; PERFORMANCE; PRESSURE VESSELS; REACTOR SAFETY; SILICON CARBIDES; STRESSES
- Descriptors DEC
- CARBIDES; CARBON COMPOUNDS; CONTAINERS; DEVELOPED COUNTRIES; ENERGY SOURCES; EUROPE; FUEL PARTICLES; FUELS; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; SILICON COMPOUNDS; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; 23 refs., 11 figs., 1 tab.
- Secondary number(s)
- HTR2018--125