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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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Fusion Science and Technology
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.
I.E. Lyublinski, V.A. Evtikhin, V.P. Krassine
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1223-1226
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-A30576
Articles are hosted by Taylor and Francis Online.
The study of tritium dissolved in liquid lithium systems containing metallic impurities is of technological interest for tritium removal processes and suppression of the tritium leakages from the blanket in a fusion reactor. The interaction parameter formalism and coordination cluster theory have been used to calculate the tritium activity coefficients in Li-T-Al, Li-T-Mg, Li-T-Si, Li-T-Y and Li-T-La systems. Calculations performed demonstrated that silicon, aluminium and magnesium have no influence on the tritium activity coefficients in dilute lithium solutions within the temperature range 400–800°C, but yttrium and lanthanum may be used to effectively decrease this coefficient in lithium melts.