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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.
Robert L. Fish
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 85-95
Technical Paper | Material | doi.org/10.13182/NT76-A31701
Articles are hosted by Taylor and Francis Online.
The effects of two notch geometries on the tensile properties of fast-neutron-irradiated, annealed Type 304 stainless steel were investigated. Notch strengthening was observed under test conditions that promote transgranular failure accompanied by significant ductility (>5% total elongation) as measured using an unnotched specimen. These conditions existed at room temperature and moderate fluence levels (∼3 to 6 x 1022 n/cm2, E >0.1 MeV, ∼3 to 6 x 1026 n/m2, E >16 fJ). No notch effect was observed at 450 and 700°F (505 and 644 K) at any fluence level investigated. A notch weakening may exist under test conditions promoting low ductility (<1.5% total elongation) intergranular failure. At a nominal tensile strain rate (2.67 x 10-3/min, 4.45 x 10 -5/s), notch weakening was exhibited near 1100°F (866 K) and neutron fluences above 3 x 1022 n/cm2 (3 x 1026 n/m2). At a nominal strain rate, the notch sensitivity is independent of notch geometry between radii of 0.003 and 0.030 in. (0.076 and 0.76 mm). The notch sensitivity becomes notch geometry dependent at higher strain rates due to higher ductilities associated with a transition in the deformation and failure mode.