ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
State legislation: Colorado redefines nuclear as “clean energy resource”
Colorado Gov. Jared Polis signed a bill into law on Monday that adds nuclear to the state’s clean energy portfolio—making nuclear power eligible for new sources of project financing at the state, county, and city levels.
M. Sharpe, W. T. Shmayda, W. U. Schröder
Fusion Science and Technology | Volume 70 | Number 1 | July 2016 | Pages 97-111
Technical Paper | doi.org/10.13182/FST15-198
Articles are hosted by Taylor and Francis Online.
The migration of tritium to the surfaces of Aluminum 6061; oxygen-free, high-conductivity copper; and Type 316 stainless steel from the bulk metal was studied using low-pressure Tonks-Langmuir argon plasma. The plasma is shown to be effective at removing tritium from metal surfaces in a controlled manner. Tritium is removed in decreasing quantities with successive plasma exposures, which suggests a depletion of the surface and near-surface-tritium inventories.
A diffusion model was developed to predict tritium migration from the bulk and its accumulation in the water layers present on the metal surface. The model reproduces the rate of tritium regrowth on the surface for all three metals and can be used to calculate the triton solubility in the water layers present on metal surfaces. The ratio of surface-to-bulk solubilities at the water layer–bulk metal interface uniquely determines the concentration ratio between these two media. Removing the tritium-rich water layers induces tritium to migrate from the bulk to the surface. This process is driven by a concentration gradient that develops in the bulk because of the perturbation on the surface.