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Division Spotlight
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.
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
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.
Mark W. Wendel, David G. Morris, Paul T. Williams
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 51-67
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35222
Articles are hosted by Taylor and Francis Online.
Loss-of-coolant accident analyses have been completed for the High-Flux Isotope Reactor safety analysis report. More than 100 simulations have been performed using the RELAP5/MOD2.5 computer program. The RELAP5 input model used for the simulations is quite detailed, including 17 parallel channels in the core region, the three active heat exchanger cells, the pressurizing system, and the secondary cooling system. Special models are developed to represent the effects of shrinkage in the primary coolant pressure boundary and cavitation of the primary coolant pumps. Six locations in the primary coolant system are selected as pipe break sites to determine the worst-case scenario. At each of the locations, simulations are completed for a range of break diameters. The reactor is assumed to survive the transient as long as the hot-spot heat flux remains below the flow excursion limit. In addition to the baseline simulations, extensive parametric simulations are conducted to ensure that the modeling assumptions used are conservative. For a break diameter of 5.1 cm at any of the six locations in the system, the hot-spot heat flux remains beneath this limit, and furthermore, no boiling occurs in the fuel region. A summary table for all results is presented, and results are discussed in detail for the worst-case 5.1-cm break scenario.