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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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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.
K.E. Wright, M.E. Oldaker, G.R. Pinter
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1672-1677
Plasma Engineering | doi.org/10.13182/FST92-A29962
Articles are hosted by Taylor and Francis Online.
A new gas delivery system is being designed to inject either tritium or deuterium gas with uniform throughput for up to 6 seconds into the TFTR Neutral Beam Long Pulse Ion Sources. Several experiments have been conducted to verify design concepts and qualify components. Piezoelectric valves were characterized for hydrogen and deuterium gas and the data used to predict operation with tritium. The uniformity of the gas throughput was studied as a function of test fluid, flowrate and initial plenum pressure. Various passive techniques to mitigate unacceptable thermal effects were tested. The uniformity of the throughput with an active pressure feedback controller was tested under various operational scenarios. The functionality of a prototypical NB D-T Gas Delivery System has been analyzed. This paper presents the results of these pre-operational tests.