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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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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.
S. Satake, H. Sawamura, M. Kimura, T. Kunugi
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 640-643
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-956
Articles are hosted by Taylor and Francis Online.
In this work, a simulation is presented that plays an important part in estimating the characteristics of cooling in a blanket used for high-temperature plasma in a fusion reactor. The objective of this study is to perform a large-scale direct numerical simulation (DNS) on the heat transfer of turbulent flow of the coolant materials assumed gas flow. The coolant flow conditions in a fusion reactor are assumed to be defined by a Reynolds number of a higher order. To investigate the effect of Reynolds number on the scalar structures, the Reynolds number based on a friction velocity and a pipe radius was set to be Reτ = 1050. The numbers of the computational grid points used for Reτ= 1050 were 2048 × 512 × 768 in the z−, r−, and ϕ-directions, respectively. In this work, details on the turbulent quantities such as the mean flow, turbulent stresses, turbulent kinetic energy budget, and the turbulent statistics were obtained.