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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
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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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.
Arkadiy A. Yukhimchuk, Vladimyr A. Arkhangel'sky
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 826-830
Design and Model | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22700
Articles are hosted by Taylor and Francis Online.
This paper presents a schematic design of Tritium Fuel Cycle for Muon-Catalyzed Intense Neutron Source (MC INS) capable of producing monochromatic 14 MeV neutrons. Based on the assumption that the fuel mixture should be used in a liquid phase the different approaches are proposed to incorporate a DT cell (synthesizer) into the MC INS facility The estimations of total tritium inventory in ihe MC INS facility are given. The calculations of the DT cell operation temperature regime using the code FLOW 3D are presented. It is shown the capability to remove the thermal energy released in the DT cell of the proposed design. The MC INS design is analyzed from the viewpoint of tritium safety requirements.
