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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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State legislation: Delaware delving into nuclear energy possibilities
A bill that would create a nuclear energy task force in Delaware has passed the state Senate and is now being considered in the House of Representatives.
Robert H. Hsu, James E. Klein
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 83-87
Technical Paper | Tritium Science and Technology - Tritium Processing, Transportation, and Storage | doi.org/10.13182/FST48-83
Articles are hosted by Taylor and Francis Online.
Palladium finely dispersed in a substrate of kieselguhr (diatomaceous earth) has been successfully used for tritium storage, separation and pumping for a number of years at the Savannah River Site (SRS). Recently SRS has designed and built a new Pd/kieselguhr flow through bed (FTB) prototype for separating tritium from other gases and simultaneously storing the tritium on palladium. The FTB prototype uses single-pass liquid nitrogen for cooling during tritium absorption/loading/storage and electrical heaters for desorption/unloading of tritium. Fourteen (14) hydrogen absorption/desorption or loading/unloading cycles have been conducted with the new FTB prototype. Test results show that all design performance objectives have been successfully achieved: recover >95% of hydrogen gas from feed gas, <5% hydrogen in discharge gas, and >99.9% hydrogen in the desorbed product gas. This paper will discuss the design and operation of the FTB, and results of performance tests such as separation efficiency, hydrogen/tritium storage capacity and temperature profiles during prep cooling, hydrogen loading and unloading.