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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
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.