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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
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.