ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.
