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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
D. Haas, J. van de Velde, H. Braun
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 100-108
Technical Paper | Material | doi.org/10.13182/NT79-A16178
Articles are hosted by Taylor and Francis Online.
In the Rapsodie-I experiment, two bundles, each containing 34 fast breeder reactor fuel pins, have been irradiated up to a peak burnup of 10.6 at.% and to a peak fast fluence (E > 0.1 MeV) of 6.65 × 1026 n/m2. One of the main objectives of this experiment was to evaluate the mechanical behavior of a bundle with spacer grids. Two types of spacer grid designs have been tested: namely, a brazed ferrule grid design and a honeycomb spot-welded grid design. The grid material was in every case niobium-stabilized austenitic stainless steel type W.Nr. 1.4981 in the annealed condition. The density and the dimensional measurements carried out on the spacer grids revealed that the geometrical changes in the grids were almost entirely due to material void swelling. In some cases, however, mechanical interactions between grids and wrapper tubes and also between fuel pins and grid cells have been emphasized. These interactions had no detrimental influence on the in-pile bundle behavior. The postirradiation mechanical tests carried out on the honeycomb spacer grids showed that the mechanical properties of the grid cells have not been significantly altered by the irradiation. A decrease of the grid material Young’s modulus has been correlated with void swelling. It has been concluded that the spacer grids operated satisfactorily despite their severe loading conditions.