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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.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Latest News
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
Yoshi Hirooka, Haishan Zhou, Naoko Ashikawa, Takeo Muroga, Akio Sagara
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 345-350
Safety, Environment, and Tritium Handling | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-514
Articles are hosted by Taylor and Francis Online.
The first wall of a magnetic fusion power reactor is defined essentially as the plasma-facing walls of blankets. For the high temperature operation of self-cooled breeder blankets, the first wall is often designed to be less than 1cm thick to reduce mechanical stresses and as a result will be subjected to bi-directional hydrogen permeation by two distinctive mechanisms; in one direction by edge plasma-driven and in the other direction by bred tritium gas-driven permeation. Using a laboratory-scale plasma device and a one-dimensional diffusion model, plasma-driven and gas-driven hydrogen permeation behavior has been investigated under some of the conditions relevant to FLiBe-employed blankets. For a 5mm F82H membrane, the plasma-driven permeation flux at ~500 eC and the gas-driven hydrogen permeation flux at ~350 CC have been measured to be of the orders of 1013 H-atoms/cm2/s and 1014 H-atoms/cm2/s, respectively. From these data one predicts that gas-driven permeation could dominate the hydrogen isotope transport through the first wall.