ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
Latest Magazine Issues
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.