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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
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
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
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.
Thomas D. Radcliff, William S. Johnson, J. Roger Parsons, Douglas E. Ekeroth
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 100-109
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34952
Articles are hosted by Taylor and Francis Online.
Formation of vortices in the lower plenum of existing nuclear power reactors has been hypothesized to cause observed localized coolant starvation, which results in a loss of thermal margin. A 1:9 scale model was built to study vortex formation and suppression in the Westinghouse AP600 advanced reactor design. Geometric similarity was maintained in the regions upstream of the reactor core. Air was used as the working fluid, and a wide range of model velocities were tested. Flow fields in the plenum were visualized with smoke injection and a tuft grid. Twin counterrotating vortices were observed. It is thought that these vortices were induced by viscous shear. The vortices were tested for sensitivity to overall reactor flow, imbalances in the individual coolant loop flows, and position of alignment keyways. Suppression of these vortices was achieved with a passive device placed in the lower plenum. The effect of this device at different axial elevations was studied.