ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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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U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Technical Session|Sponsored by THD
Wednesday, June 10, 2020|3:35–5:20PM (4:35–6:20PM EDT)
Prashant Jain (ORNL)
Igor Bolotnov (NCSU)
Janice Lindegard (American Nuclear Society)
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Validation of the 1-D Thermal Stratification Model in Gallium Environment
Cihang Lu (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.), Brendan Ward (Kansas State Univ.), Hitesh Bindra (Kansas State Univ.)
Cooling Channel Optimization in Additively Manufactured Gas-Cooled Reactor Core
Justin Weinmeister, Prashant K. Jain
Multi-Scale & Multi-Physics Analysis of PWR Steam Line Break Accident
Jae Ryong Lee (KAERI), Han Young Yoon (KAERI), Ik Kyu Park (KAERI)
Sodium Fire Models for In- and Ex-vessel Safety Analysis Code SPECTRA
Mitsuhiro Aoyagi (Japan Atomic Energy Agency), Akihiro Uchibori (Japan Atomic Energy Agency), Takashi Takata (Japan Atomic Energy Agency), Hiroyuki Ohshima (Japan Atomic Energy Agency)
Code Validation for SBLOCA Test of PHWR using MARS-KS
Kyunglok Baek (Korea Institute of Nuclear Safety), Seon Oh Yu (Korea Institute of Nuclear Safety)
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