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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Kuo-Tong Ma, Yuh-Ming Ferng, Yin-Pang Ma
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 90-102
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT98-A2882
Articles are hosted by Taylor and Francis Online.
Flow-accelerated corrosion (FAC) is a piping degradation mechanism resulting in the loss of material from the inside of the piping that subsequently thins the wall. The FAC that causes costly plant repairs and personal injuries is generally accelerated by the single-phase fluid or two-phase mixture, which seems to be a very serious problem found in most of the power plants these days. Based on the measured data of pipe thickness, FAC phenomenon strongly depends on the piping layout and local flow conditions. A three-dimensional two-phase model is proposed with the aim of simulating two-phase behaviors found in the pipe and investigating the impact of these local parameters on FAC damage. Through three-dimensional calculation, liquid droplet impingement was found to dominate the FAC damage occurring in high-steam-quality flow. A simplified parameter is proposed to express an indicator of this normal impingement force. The magnitude of this parameter can represent the severity location of the FAC damage. Compared with plant-measured data of the wear rate, the predicted locations of serious FAC are in good agreement qualitatively. In addition, the phenomenon that different piping layouts will induce different FAC locations can be accurately captured in the current mode.