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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Fusion Science and Technology
May 2025
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.
Marie-Françoise Maday
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 596-601
Fusion Materials | doi.org/10.13182/FST01-A11963302
Articles are hosted by Taylor and Francis Online.
Load-controlled low cycle fatigue tests were carried out on the reduced activation martensitic steel, F82H modified, in pure oxygen-free water at 240°C, thus simulating the most viable coolant chemistry for fusion reactors. It was found that water determined cyclic life reduction as compared to the base-line data in air. Depending on the mechanical parameters employed, the fracture modes were either of the fatigue type and associated with subcritical crack nucleation and stable propagation assisted by the aqueous environment, or almost completely plastic due to the onset of deformation instability which preceded any environmentally-induced cracking process.
The results presented in this paper will be discussed in terms of individual concurrent damaging mechanisms, either time or cycle dependent. Possible causative factors are also suggested for further assessments concerning the cyclic response variability observed in specimens from different lots having, a priori, the same history.