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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Chiaki Kino, Yoshihiro Morita, Masao Chaki (The Inst of Applied Energy)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 201-211
Reactor core isolation cooling system (RCIC) is designed to operate using saturated steam extracted from a main steam line. On the other hand, RCIC in Unit-2 of Fukushima Daiichi Nuclear Power Plant was activated before the tsunami hit and continued to operate under two phase flow conditions during the accident. When RCIC continuously operates without control by electric power, reactor water level would reach the main steam line resulting in turbine efficiency degradation and subsequent RCIC stop. The mechanism for RCIC of Unit-2 to have continuously operated under such two phase flow conditions is still unclear. Currently, a project is progressing to understand the true operating limitations of RCIC system under beyond design basis event. The Institute of Applied Energy is developing the new RCIC system model for the SAMPSON code in the project. The present paper proposes a trial model for RCIC system under two phase flow conditions. The model takes the effect of quality and pressure on turbine efficiency into consideration. SAMPSON calculation based on the model could reproduce qualitatively RPV pressure behavior of Fukushima Daiichi Unit-2 accident. However there are many uncertainties, such as water temperature of S/P, isentropic efficiency, and so on, so the model will be improved based on experiment and CFD results planned in the project.