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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Hiroaki Suzuki, Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Soji Koikari, Kunio Hasegawa, Fumio Kojima, Seiichi Koshizuka, Derek H. Lister
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 194-209
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A18111
Articles are hosted by Taylor and Francis Online.
The possibility of thousands of flow-accelerated-corrosion (FAC) zones causes long and costly inspection procedures for nuclear, as well as fossil-fuel power plants, even if the number of zones is minimized on the basis of temperature and flow velocity. In order to decrease the number of inspection zones, suitable prediction or estimation procedures for FAC occurrence should be applied, and the resulting computer programs should be tuned with as many inspection data as possible. Such coupling of the estimation and inspection procedures should allow effective and reliable preparation to be made against FAC occurrence and propagation.This paper defines the FAC risk as the mathematical product of the possibility of the occurrence of wall thinning and its hazard scale. The possibility of the occurrence of wall thinning was designated as the time margin for pipe rupture determined by applying a one-dimensional FAC code, which could predict the wall-thinning rate with an accuracy within a factor of 2, while the hazard scale was defined as the volume of effluent steam and water from the ruptured mouth, which was enthalpy of water originally flowing in the pipe multiplied by the square of the pipe inner diameter. High FAC risk zones along entire cooling systems could be evaluated in only one-tenth or one-hundredth of the computer time as for a three-dimensional FAC code to determine the priority for inspection-order importance.