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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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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.
Yuh-Ming Ferng, Yin-Pang Ma, Kuo-Tong Ma, Nien-Mien Chung
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 319-330
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT99-A2977
Articles are hosted by Taylor and Francis Online.
Flow-assisted corrosion (FAC), an aspect of erosion/corrosion (E/C), is a mechanism of piping degradation that causes a loss of material from the inside of the piping and then thinning of the wall. FAC damage is believed to be accelerated by a single- or two-phase mixture flowing within the piping. A physical model is presented that attempts to predict the distributions of sites of FAC wear within the fitting; this model includes the E/C and the three-dimensional single- or two-phase-flow models. Based on the calculated results, the impact of centrifugal and gravitational forces on liquid droplet behavior can be reasonably simulated. Appropriate indicators derived from the E/C model are used to predict the FAC locations. Compared with the plant measured results, the proposed model can precisely predict the distribution of wear sites. The FAC pattern dominated by the upstream fittings can also be determined. The satisfactory agreement reveals that the indicators provided by the current models can be used to reasonably predict the FAC locations and explain the complicated phenomenon of FAC wear occurring within the fittings.