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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
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
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Futaba Ono, Michio Yamawaki, Satoru Tanaka
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1250-1255
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30581
Articles are hosted by Taylor and Francis Online.
Regrowth in tritium desorption from type 316 stainless steel, copper and borosilicate glass was studied. It was found that the tritium, which was penetrated into materials by long term contact, could not be easily desorbed by a stream of nitrogen gas (dry, wet or 10 % H2) at room temperature. The ratio of the tritium amount desorbed from surface by each purging to the tritium concentration in the gaseous phase under the sorption /desorption equilibrium on the surface was found to be constant through the repeated desorption. The amount of tritium desorbed by each gas purging was found to decrease by repeated desorption.