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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.
T. J. Walker
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Page 189
Material | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT74-A31451
Articles are hosted by Taylor and Francis Online.
A quantitative strain-and-stress state criterion for failure has been developed which is applicable in the vicinity of sharp cracks. This criterion is applicable to any example which may be represented by finite element theory in the detail required to determine the strain-and-stress state for the crack tip region. The restriction of linear elastic fracture mechanics which defines a minimum crack length is removed, since the influence of the free boundary in the vicinity of the crack is included in the finite element solution. The development of the criterion includes an experimental base and demonstrates the applicability for the conditions of a “sharp” fatigue crack and for a “blunt” machined notch with an ∼0.001-in. tip radius.