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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
Wei Tang, Jian Chen, Brian Gibson, Roger Miller, Scarlett Clark, Mark Vance, Zhili Feng, Keith Leonard (ORNL), Jonathan Tatman, Benjamin Sutton, Gregory Frederick (EPRI)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 67-75
Welding is widely used for repair, maintenance, and upgrade of nuclear reactor components. As a critical technology for supporting the extension of nuclear power plant service lifetimes beyond 60 years, there has been an industry need in further developing welding technology for highly irradiated materials. During welding of irradiated materials, Helium, which is a transmutation byproduct from Boron and Nickel contained in the structural alloys, can coalesce into bubbles along grain boundaries in the material under driving forces of high temperature and thermal tensile stress. This leads to embrittlement and potential intergranular cracking in the Heat Affected Zone (HAZ) of the weld. In this paper, irradiated 304 stainless steel coupons containing 5, 10 and 20 ppm Boron prior to radiation were successfully welded by advanced laser beam welding (LBW) and friction stir welding (FSW). Facilities and welding machine design, welding processes development, cold material welded joints evaluation, process safety control and documentation, and irradiated material welding are discussed. Both laser and friction stir welded coupons of the irradiated material exhibited high welding quality and surface finish. No Helium induced welding defects were observed on the weld surfaces or adjacent base metals.