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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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Zhiee Jhia Ooi, Vineet Kumar, Caleb S. Brooks (Univ of Illinois)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 88-97
A new database of natural circulation in a vertical annulus is under development in the Multiphase Thermofluid Dynamics Laboratory (MTDL) at the University of Illinois at Urbana-Champaign. The focus of the dataset is on the two-phase phenomena of boiling, condensing, flashing, and saturated flow in a vertical channel under natural circulation. The 5.03 m annular test section with inner and outer diameter of 19.1 mm and 38.1 mm respectively houses a 3 m internally heated annular section followed by a 2.03 m unheated annular section. Five measurement ports, two in the heat section, one at the heated to unheated boundary, and two in the unheated section provide measurement of pressure and local measurements of void fraction, interfacial area concentration, gas velocity, Sauter mean diameter, and liquid temperature. Additional pressure and liquid temperature measurements are provided at important locations around the natural circulation loop. The dataset is designed for validation of one-dimensional system codes under natural circulation for pressures up to 1 MPa, which are important to passive cooling approaches to reactor safety.