Improvements in the fabrication of HTR fuel elements
Creators
- 1. NUKEM Technologies GmbH, Industriestrasse 13, 63755 Alzenau (Germany)
- 2. FNAG Furnaces Nuclear Applications Grenoble S.A.S., Wilhelm-Rohn Strasse 35, 63450 Hanau (Germany)
- 3. ALD Vacuum Technologies GmbH, Wilhelm-Rohn Strasse 35, 63450 Hanau (Germany)
Description
The application of High Temperature Reactor (HTR) Technology in the course of the continuously increasing world wide demand on energy is taken more and more under serious consideration in the power supply strategy of various countries. Especially for the emerging nations the HTR Technology has become of special interest because of its inherent safety feature and due to the alternative possibilities of applications, e.g. in the production of liquid hydrocarbons or the alternative application in H2 generation. The HTR fuel in its various forms (spheres or prismatic fuel blocks) is based on small fuel kernels of about 500 μm in diameter. Each of these uranium oxide or carbide kernels are coated with several layers of pyrocarbon (PyC) as well as an additional silicon carbide (SiC) layer. While the inner pyrocarbon layer is porous and capable to absorb gaseous fission products, the dense outer PyC layer forms the barrier against fission product release. The SiC layer improves the mechanical strengths of this barrier and considerably increases the retention capacity for solid fission products that tent to diffuse at these temperatures. Especially the high quality German LEU TRISO spherical fuel based on the NUKEM design, has demonstrated the best fission product release rate, particular at high temperatures. The ∼10% enriched uranium triple-coated particles are embedded in a moulded graphite sphere. A fuel sphere consists of approximately 9 g of uranium (some 15,000 particles) and has a diameter of 60 mm. As the unique safety features, especially the inherent safety of the HTR is based on the fuel design, this paper shall reflect the complexity but also developments and economical aspects of the fabrication processes for HTR fuel elements.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.10.036Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.10.036;
- PII
- S0029-5493(11)00909-5;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 251
- Journal Page Range
- p. 239-243
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 5. international topical meeting on high temperature reactor technology
- Acronym
- HTR 2010
- Dates
- 18-20 Oct 2010
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44047500
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COATED FUEL PARTICLES; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL ELEMENTS; GRAPHITE; HTGR TYPE REACTORS; HYDROCARBONS; HYDROGEN PRODUCTION; MODERATELY ENRICHED URANIUM; POROUS MATERIALS; PYROLYTIC CARBON; REACTOR SAFETY; SILICON CARBIDES; SLIGHTLY ENRICHED URANIUM; URANIUM CARBIDES; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CARBIDES; CARBON; CARBON COMPOUNDS; CHALCOGENIDES; ELEMENTS; ENRICHED URANIUM; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; METALS; MINERALS; NONMETALS; ORGANIC COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; SAFETY; SILICON COMPOUNDS; URANIUM; URANIUM COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.