ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
D. Wootan, R. Omberg, A. Casella, N. Lahaye, B. Mcdowell (PNNL), W. Stokes (Columbia Basin Consulting Group)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 36-44
The accident scenarios that need to be analyzed within Chapter 15 of a safety analysis report may vary significantly between advanced reactors and the light water reactors that compose the current commercial fleet. In anticipation of identifying scenarios of concern and developing methods for their analysis, correlations may be made to calculations and tests performed in support of the liquid metal and molten salt reactors that have been operated previously within the US. In this paper, we discuss efforts made to compare Chapter 15 considerations for a proposed lead-bismuth cooled reactor to those developed previously for the Fast Flux Test Facility (FFTF) and the GE-Hitachi PRISM reactor. Comparisons were also made with Beyond Design Basis Accidents for FFTF.
