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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
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.
Chang H. Oh, John C. Chapman
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 327-337
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35212
Articles are hosted by Taylor and Francis Online.
Flow experiment and analysis were performed to determine flow instability condition in a single thin vertical rectangular flow channel (1.98 mm in channel gap, 50.8mm in width, and 121.92 or 60.96 cm in heated height), which represents one of the Advanced Test Reactor’s inner coolant channels between fuel plates. The maximum surface heat flux and flow rate are 159.8kW/m2 and 462.5 kg/s-m2, respectively, which simulates decay heat removal from the single heated surface of the Advanced Test Reactor. The tests are conducted at atmospheric and subatmospheric pressure, simulating expected conditions during a hypothetical loss-of-coolant accident. The precursor of the flow instability [the point of net void generation and the onset of flow instability (OFI) defined by Saha and Zuber] was compared, and the OFI map (power density versus minimum mass flux at OFI) was developed in this study.