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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
Timm Preusser
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 343-371
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26303
Articles are hosted by Taylor and Francis Online.
For a number of reasons, over the past ten years, much interest has been shown in developing the concept of advanced fuel in liquid-metal fast breeder reactors alongside the classical oxide fuel rod. To describe those concepts theoretically, the integral fuel rod code URANUS was extended to include a carbide fuel version. All the relevant material properties— thermal, mechanical, and irradiation-induced—for UC and (U,Pu)C were taken into account. Material data were extracted from published literature and after careful comparison were assessed and correlated. The models for solid body and gas bubble swelling and for fission gas release are newly developed and calibrated to accessible data. Together with the standard routines of URANUS for calculating temperatures, geometry in hot state, stresses, strains, crack mechanics, plasticity, gap conductance and burnup, and with the axial coupling of individual sections, a detailed description is available for precalculation and interpretation of carbide rod experiments.