Author: W. J. KuceraPublisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 61
Book Description
Specifications and Procedures Used in Manufacturing U3O8-aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor
Author: W. J. KuceraPublisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 61
Book Description
Specifications and Procedures Used in Manufacturing U$sub 3$O$sub 8$- Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A thin plate-type element containing a dispersion of 20% enriched U/sub 3/O/sub 8/ was developed and successfully used in the 5-Mw pool-type research reactor at the Puerto Rico Nuclear Center. The underlying criteria that guided the design are presented. The technological factors, such as compatibility, corrosion resistance, and irradiation behavior, which led to the selection of U/ sub 3/O/sub 8/ as the fissile compound and aluminum as the cladding and matrix material, are reviewed. The fabrication procedures developed and adopted for manufacturing the component are presented. The scheme involves incorporation of 55 wt% U/sub 3/O/sub 8/ into aluminum compacts by powder metallurgy techniques, preparation of composite fuel plates by roll cladding, assembly of fuel plates into an integral unit by either the roll-swaging or pinning techniques, and corrosion protection of the element by an anodizing treatment to increase service life. Quality control measures adopted to ensure dimensional tolerances are described. Mechanical joining proved to be an economical method for assembling the pool-type fuel elements within dimensional specifications. (auth).
Properties of U Sub 3 O Sub 8 -aluminum Cermet Fuel
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Nuclear fuel elements containing U3O dispersed in an aluminum matrix have been used in research and test reactors for about 30 years. These elements, sometimes called cermet fuel, are made by powder metallurgical methods (PM) and can accommodate up to approximately 50 wt % uranium in the core section of extruded tubes. Cermet fuel elements have been fabricated and irradiated at the Savannah River Site (SRS). Irradiation behavior is excellent. Extruded tubes with up to 50 wt % uranium have been successfully irradiated to fission densities of about 2 × 1021 fissions per cc of core. Physical, mechanical, and chemical properties of cermet fuels are assembled into a reference document. Results will be used by Argonne National Laboratory to design cermet fuel elements for possible use in the New Production Reactor at SRS. 57 refs., 33 figs., 12 tabs.
Author: G. L. Copeland