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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
Philipp Schaedle, Nicolas Hubschwerlen, Holger Class
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 188-197
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-82
Articles are hosted by Taylor and Francis Online.
The long-term safety performance of a potential deep geological repository for high-level and intermediate-level long-lived nuclear waste is studied through a numerical simulation program that requires simulation tools capable of modeling appropriately the phenomenologies of interest in the repository and its environment. Because of the complexity of the modeled layout, the numerous physical processes involved, and the simulated times (up to one million years), the computational needs are very high. TOUGH2-MP is a very suitable tool for modeling the impact that the heat and gas generated in the emplacement areas may have on the evolution of the fluid pressure and on the saturation fields in the repository's drifts and shafts as well as in the host rock itself. The module EOS7R also gives the possibility to compute a coupled radionuclide transfer. Regarding computational efficiency, it is of interest to decouple the transport from the hydraulic calculation for three main reasons. First, this allows the hydraulic calculation to be used once for several transport computations of a performance analysis and safety assessment study, which is expected to lead to a substantial gain in CPU time. Second, it allows optimization of the discretization separately for both hydraulic and transport calculations. Third, it allows combination of the TOUGH2 hydraulic and other codes modeling radionuclide transport, which allows consideration of phenomenologies that are not available in TOUGH2. This work shows how to establish a sequential approach between TOUGH2 and another code. It presents the conditions of use of such an approach, in terms of performance and the impact of the temporal discretization on the results.