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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May 2025
Nuclear Technology
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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.
Daniel Cubicciotti, B. C. Syrett, R. L. Jones
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 720-723
Technical Note | Material | doi.org/10.13182/NT81-A32816
Articles are hosted by Taylor and Francis Online.
The effect of surface condition on the initiation of iodine-induced stress corrosion cracks in Zircaloy tubing was investigated. The internal surface of the Zircaloy tubing was given one of three surface treatments, namely etching, grit blasting, or shot blasting. Each of these treatments can readily be performed commercially on Zircaloy fuel cladding. Specimens of surface-treated tubing were locally stressed in an iodine environment at 590 K by indenting the outer surface of the tube wall with a small steel ball. The crack initiation pattern on the inner surface was examined in a scanning electron microscope. Crack initiation was found to be least developed for etched surfaces, was most developed for shot-blasted surfaces, and was developed to an intermediate degree for grit-blasted surfaces. Apparent anomalies between these crack initiation data and the time to failure data obtained previously in tube pressurization tests are rationalized on the basis of the cracking processes.