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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.
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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
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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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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.
G. F. Taylor, D. P. Dautovich
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 30-36
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32829
Articles are hosted by Taylor and Francis Online.
The performance of Canadian deuterium uranium (CANDU) nuclear steam generators has been outstanding. In the 88 reactor years of operation that ended in August 1980, only 61 of ∼300 000 tubes have been plugged and only 12 of these were in large commercial units. This excellent performance is ascribed to the high recirculation ratio and very open tube support design of the steam generators and the relatively noncorrosive cooling water at most sites. In May 1979, 37 tubes were plugged at the Ontario Hydro Nuclear Power Demonstration (NPD) Nuclear Generating Station. The location of the defects suggests they may be the first corrosion-induced failures in a CANDU steam generator. Chemical cleaning of the NPD steam generator in November 1979 resulted in the removal of 900 kg of deposits, cleaning of the tubes, and a return to full-power capability. Examination of a steam generator removed from the Douglas Point Generating Station (GS) in 1977 has revealed corrosion of carbon steel tube support plates and Monel 400 tubes but no denting. No tubes have been plugged at Pickering since the manufacturing defect discovered in 1974. Two of the 11 Inconel 600 tubes plugged at Bruce GS in 1977 and 1979 had leaked at tube-to-tubesheet seal welds, and others showed primary side tube wall defects, the cause of which has not been determined. Specification of low cobalt Inconel 600 has contributed to a tenfold reduction in 60Co radiation fields at Bruce compared with Pickering. To ensure good performance from steam generators at seawater-cooled stations, corrosion-resistant tube supports, high integrity condensers, and automated steam generator chemistry control have been installed