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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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.
Zhilin Chen, Masao Matsuyama, Shinsuke Abe, Shuming Peng
Fusion Science and Technology | Volume 70 | Number 3 | November 2016 | Pages 461-467
Technical Note | doi.org/10.13182/FST15-151
Articles are hosted by Taylor and Francis Online.
Beta-induced X-ray spectrometry (BIXS) is a nondestructive method to detect tritium both on the surface and in the bulk of materials. The effects of internal bremsstrahlung (IB) from the beta decay of tritium on tritium profile reconstruction have been theoretically studied by numerical simulation based on Matlab code. Three kinds of samples, two polymers [(T-C4H6O2)n, Zeff = 6.4, homogeneous and heterogeneous] and one zirconium, with different tritium depth profiles were used in the calculations, and two of them were confirmed by experiments. The results indicate that the intensity of IB is comparable with external bremsstrahlung (EB) for low-Z materials, and the intensity of IB decreases a little faster than that of EB for the same material. Neglecting IB would lead to as much as 12% counts loss in tritium profile reconstruction for a polymer sample, and it is expected to be more serious for lower-Z materials such as beryllium and carbon fiber composites. The results also show that for the same material, the influence of IB depends on the depth profile of tritium in the sample.