ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
H. G. A. Bates
Nuclear Technology | Volume 66 | Number 2 | August 1984 | Pages 415-428
D.Gas/Metal Reaction | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33444
Articles are hosted by Taylor and Francis Online.
A corrosion program is being carried out to establish the long-term corrosion behavior of candidate alloys for the prototype nuclear process (PNP) reactor primary circuit. Results are presented for corrosion tests performed in impure helium over the temperature range of 700 to 900 °C for times up to 10000 h. In the helium atmosphere containing 0.5 to 1.5 μbar H2O, 15 μbar CO, 20 μbar CH4, and 500 μbar H2, the three main PNP reference alloys—Inconel-617, Nimonic-86, and Hastelloy-X—exhibit excellent corrosion resistance with the carbon uptakes of <0.02% in 10 000 h at temperatures up to 900°C. Differences in behavior are related to the composition and morphology of protective surface scales and minor variations in gas impurity levels during test startup. The influence of variations in alloy composition on the long-term stability of these oxide scales is also discussed.