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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.
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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
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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
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
P. W. Fisher, M. J. Gouge
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 515-520
Fueling and Tritium Handling Technology (Poster Session) | doi.org/10.13182/FST98-A11963664
Articles are hosted by Taylor and Francis Online.
As part of the International Thermonuclear Experimental Reactor (ITER) plasma fueling development program, Oak Ridge National Laboratory has fabricated a pellet injection system to test the mechanical and thermal properties of extruded tritium. This repeating single-stage, pneumatic, Tritium-Proof-of-Principle Phase II (TPOP-II) Pellet Injector has a piston-driven mechanical extruder and is designed to extrude and accelerate hydrogenic pellets sized for the ITER device. Tritium and deuterium-tritium (D-T) pellets have been produced in experiments at the Los Alamos National Laboratory Tritium Systems Test Assembly. About 38 g of tritium was used in the experiment. This paper presents results of the TPOP-II extrusion experiments. These extrusion experiments indicate that both T2 and D-T will require higher extrusion forces than D2 by about a factor of 2 and that the flow of the material may be characterized by static and dynamic shear strengths.