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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
Framatome, KHNP to investigate producing Lu-177 in South Korea
Framatome and Korea Hydro & Nuclear Power (KHNP) announced the signing of a memorandum of understanding to explore the possibility of producing the medical isotope Lutetium-177 at KHNP’s Wolsong nuclear power plant in South Korea. The companies also will investigate the feasibility of using the plant to support Korean production of medical radioisotopes in the future.
Paul Korinko, Richard Wyrwas, William Spencer, Brent Peters, Edward Stein, Dale Hitchcock
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 403-409
Technical Note | doi.org/10.1080/15361055.2017.1293415
Articles are hosted by Taylor and Francis Online.
Tritium is highly reactive with many materials. It is adsorbed onto and absorbed through the surface of containment vessels subsequently modifying the contained gas composition by isotopic exchange and catalytic reactions with surface elements and adsorbed gas species. Savannah River Tritium Enterprise (SRTE) uses a proprietary surface treatment that is intended to render the surface inert. Unfortunately, this process has not proven to be sufficiently robust for containing tritium gas standards. SRTE has funded a project that will explore the effects of electropolishing and vacuum and oxidizing thermal treatments on surface passivation of stainless steel (SS). Herein, a statistically designed series of experiments will be discussed that will inform optimized parameters for acid composition, current density, and other electrochemical process variables for the passivation of SS. The surfaces were analyzed using Laser Induced Breakdown Spectroscopy (LIBS), Auger Electron Spectroscopy (AES), Atomic Force Microscopy (AFM), and Scanning Electron Microscopy (SEM). Novel techniques to characterize the passive layers are also being developed. In future experiments, gas sample bottles will be loaded with protium and deuterium to determine the relative exchange characteristics of the treated vessels. Previous work has indicated that if little protium ingrowth occurs or few contaminant species form, e.g., methane or ammonia, and little hydrogen exchange occurs in a protium and deuterium gas mixture the treatment is suitable for maintaining the tritium stability. This statement is not intended to imply that tritium, deuterium, protium mixes will not exchange, only that these results are useful as a screening tool prior to tritium exposure.