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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.
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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
Countering the nuclear workforce shortage narrative
James Chamberlain, director of the Nuclear, Utilities, and Energy Sector at Rullion, has declared that the nuclear industry will not have workforce challenges going forward. “It’s time to challenge the scarcity narrative,” he wrote in a recent online article. “Nuclear isn't short of talent; it’s short of imagination in how it attracts, trains, and supports the workforce of the future.”
L.L. Lengyel, K. Borrass
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1760-1765
Plasma Heating, Impurity Control, and Fueling | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40015
Articles are hosted by Taylor and Francis Online.
The fueling requirements of fusion reactors are analyzed on the basis of a recent assessment performed for NET (Next European Torus). Results of penetration depth calculations applied to single pellets under thermonuclear plasma conditions are described. Data corresponding to the commonly used neutral gas shielding ablation model and a magnetic shielding approximation are compared. The pellet size and pellet velocity requirements for central fueling are established. Scenario calculations are performed with the help of a 1D tokamak transport code. The pellet size, pellet velocity, and injection frequency requirements for continuous fueling or, for example, ignition with the help of pellets are obtained. The effect of runaway electrons, NB ions and alpha particles is estimated by calculating the ablation rates caused by these particles in fusion plasmas and comparing them with the ablation rate induced by thermal electrons.