Performance Evaluation of Modern HTR TRISO Fuels
Description
This report is a compilation of experience and results with TRISO-coated particles in spherical fuel elements. Its emphasis is on the application of these fuels in modular pebble-bed High Temperature Reactors (HTRs) with coolant exit temperatures up to 1000°C. Chapter 0 is a short assessment of attainable burn-up with modern HTR fuel particles. Chapter 1 is an introduction to the modular HTR and its fuel. This chapter also spells out fuel specifications and fuel requirements specifically tailored to the 200 MWth steam-generating MODUL and the 170 MWth process-heat MODUL. Chapter 2 describes fuel manufacture and quality assurance. Chapter 3 goes into details of the extensive German irradiation testing programs during the last decade with modern, high-quality, TRISO-coated particle fuels. Chapter 4 deals with heating test for accident simulation. Chapter 5 covers the current status of fuel performance modeling and fission product release predictions methods up to the fuel element surface. Chapter 6 covers a wide range of aspects pertaining to the graphite matrix used in spherical fuel elements. . Appendix A spells out the fission product source terms derived from free uranium in the fuel elements due to manufacture. Appendix B describes silicon carbide as the most important material in HTR fuel. Appendix C explains the PANAMA code for coated particle failure predictions.
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52011643.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 529 p.
- Report number
- KFA-HTA-IB--5/90
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52011643
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; FEDERAL REPUBLIC OF GERMANY; FISSION PRODUCT RELEASE; FORSCHUNGSZENTRUM JUELICH; FUEL ELEMENTS; FUEL PARTICLES; GRAPHITE; HTGR TYPE REACTORS; QUALITY ASSURANCE; REACTOR ACCIDENTS; URANIUM
- Descriptors DEC
- ACCIDENTS; ACTINIDES; CARBON; DEVELOPED COUNTRIES; ELEMENTS; EUROPE; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; MANAGEMENT; METALS; MINERALS; NATIONAL ORGANIZATIONS; NONMETALS; QUALITY MANAGEMENT; REACTOR COMPONENTS; REACTORS; SIMULATION; WESTERN EUROPE
Optional Information
- Notes
- Figs., tabs.; Document from Juelich Preservation Project