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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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Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Azar P. Majidi, Michael A. Streicher
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 356-369
Technical Paper | Material | doi.org/10.13182/NT86-A33848
Articles are hosted by Taylor and Francis Online.
Three different electrochemical reactivation tests are compared with etch structures produced in the electrolytic oxalic acid etch test. These nondestructive tests are needed to evaluate welded stainless steel pipes and other plant equipment for susceptibility to intergranular attack. Sensitization associated with precipitates of chromium carbides at grain boundaries can make these materials subject to intergranular attack in acids and, in particular, to intergranular stress corrosion cracking in high-temperature (289°C) water on boiling water nuclear reactor power plants. In the first of the two older reactivation tests, sensitization is detected by the electrical charge generated during reactivation. In the second, it is measured by the ratio of maximum currents generated by a prior anodic loop and the reactivation loop. A third, simpler reactivation method based on a measurement of the maximum current generated during reactivation is proposed. If the objective of the field tests, which are to be carried out with portable equipment, is to distinguish between nonsensitized and sensitized material, this can be accomplished most simply, most rapidly, and at lowest cost by an evaluation of oxalic acid etch structures.