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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Hasna J. Khan, George Kosaly
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 34-45
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15975
Articles are hosted by Taylor and Francis Online.
Void fraction calculations have been performed using the subchannel drift-flux code CANAL. Using void and flow distributions in rod bundle geometry, a value of C0 has been estimated for bundle-averaged void fraction calculation in one-dimensional approximations. Successful prediction of the average void fraction is observed for the annular rod bundle geometry of the FRIGG experiment. In order to perform subchannel void fraction calculation, a C0 model has been developed for one-dimensional subchannel geometry. The implicit form of the C0 model developed accounts for void and flow conditions in the adjacent subchannels existing at the common interfaces, i.e., at the gap spacing between the subchannels. It appears that the magnitude of C0 varies between subchannels (annular rings of FRIGG geometry) but remains almost constant within each subchannel. Good agreement is observed between prediction and data for subchannel void fractions in axially uniform and nonuniform heated rod bundles.