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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Nuclear Science and Engineering
July 2025
Nuclear Technology
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Yassin A. Hassan
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 257-267
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33609
Articles are hosted by Taylor and Francis Online.
Three-dimensional fluid and thermal mixing analysis of a full-scale cold leg and downcomer of a Babcock & Wilcox-designed pressurized water reactor is performed. The impetus of the present study is to provide an accurate estimation of the local fluid temperatures in the cold leg and downcomer when the cold high-pressure safety fluid is injected into the cold leg carrying a hot fluid. Such temperature predictions are needed in resolving the so-called pressurized thermal shock issue in the nuclear industry. The unique feature of this study is the use of the accurate mass-flow-weighted skew-upwind scheme to approximate the convective transport terms in the COMMIX-1A code approximation of the fluid energy equation. This new scheme is shown to considerably reduce the false diffusion that plagued multidimensional thermal-hydraulic applications. The computed fluid velocity patterns and temperature predictions have shown similar behavior to the flow visualization and temperature field measurements in scaled experiments.