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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
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.