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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
T. D. Radcliff, J. R. Parsons, W. S. Johnson, A. E. Ruggles
Nuclear Science and Engineering | Volume 131 | Number 3 | March 1999 | Pages 426-438
Technical Paper | doi.org/10.13182/NSE99-A2044
Articles are hosted by Taylor and Francis Online.
An existing geometric and fluid-fluid scaled facility is applied to investigate the transport of borated safety injection (SI) fluid in the Westinghouse AP600 reactor vessel during a main steam-line rupture (MSLR) event. The AP600 reactor has coaxial injection into the vessel downcomer rather than the cold-leg cross-flow injection typical of operating power reactors. This gas-flow test facility has unique detail in the representation of the SI nozzle-to-core inlet path most important to SI transport. Analysis of the transport phenomena expected in the reactor and the scaled facility, given MSLR conditions, indicates that both buoyancy and turbulent diffusion can have comparable influences on SI transport. It is shown that different reactor-to-experiment velocity ratios are required to scale each phenomenon. Tests are performed to evaluate transient SI fluid concentration at the core inlet using the appropriate velocity ratios to scale buoyancy and diffusion. Two asymmetric loop-flow boundary conditions representative of the MSLR event as well as a symmetric flow condition are applied. While no one test result is fully similar to the expected reactor transport, this ensemble of tests provides data that are valuable for AP600 numerical model benchmarking.