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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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August 2024
Nuclear Technology
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Latest News
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Jayan K. George, Jagdeep B. Doshi
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 338-349
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35016
Articles are hosted by Taylor and Francis Online.
The pressure disturbance propagation through a weakly compressible medium, bound by rigid structure as well as material interfaces, has an important bearing on the safety analysis of liquid-metal-cooled fast breeder reactors. The analyses have been carried out using numerical algorithms based on Eulerian, Lagrangian, or mixed formulations. Even though the results obtained from these schemes compared well with the benchmark experimental results, certain drawbacks, such as less accurate treatment of material interfaces in the Eulerian schemes and mesh distortion in the La-grangian schemes, and so forth, remain. These drawbacks may be overcome by using a method of characteristics in two dimensions known as the near-characteristic method to solve the problem. The region of interest is discretized into Eulerian grids, and the flow parameters are obtained from the compatibility equations corresponding to the near characteristics generated from the grid points. The material interfaces are tracked explicitly, using the near-characteristic scheme. The scheme is used to analyze a typical core disruptive accident problem, and the results are compared with experimental results as well as those ob. tained using two other numerical schemes. Good agreement is observed among the results; indeed, the one-dimensional problem of exploding wire phenomena and the two-dimensional problem of core disruptive accident analysis validate the effectiveness of the scheme. The future extension of the present scheme will include fluid structure interaction and complex internal structures.