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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Apr 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
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.
Xiang Wang (Harbin Eng Univ), Chunyu Liu, Rafael Macián-Juan (Technical Univ of Munich)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 460-468
The Dual Fluid Reactor is a molten salt fast reactor developed by IFK (Institut fuer Festkoerper-Kernphysik) based on the Gen-IV Molten-Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor (SFR, LFR) concepts. This analysis report focuses on the comparison between previ-ous coupled calculations of the system with the default fuel salt of U-Pu mixture and new one with a transurani-um (TRU) fuel salt option. An approach to the dynamics and stability analysis of the DFR by using the well-developed linear method with their improved modifica-tions is proposed. The coupled one-dimensional neutron-ics and thermal-hydraulic model will be established with this method. With this model the steady state and the dy-namics analysis of the system under various operational conditions are presented. The stability of the system will be also analyzed with the results in the parametric studies. The results are compared with Molten Salt Breeder Reac-tor (MSBR) and Molten Salt Fast Reactor (MSFR), which can be decisive for the future application of the DFR.