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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.
James M. Kennedy, Ted B. Belytschko, Daniel F. Schoeberle
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 290-302
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32568
Articles are hosted by Taylor and Francis Online.
The STRAW code was developed for the analysis of core components subjected to high-pressure transients. It is a finite element code that models both the fluid and structures. The code is able to treat material nonlinearities and geometric nonlinearities due to large displacements. The fluid model uses a quasi-Eulerian element, which enables nodes to be moved independently. Time integration is by the explicit central difference method. Although the code was designed for the study of core mechanics, it is applicable to a wide variety of problems because it uses a finite element format. The STRAW calculations for a Stanford Research Institute cluster experiment show that reasonable predictions can be made of the maximum strains in the structures.