ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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May 2025
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.
J. F. Remark, A. B. Johnson, Jr., Harry Farrar, IV, D. G. Atteridge
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 369-377
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31601
Articles are hosted by Taylor and Francis Online.
The results of a study on the use of the decay of tritium to helium as a method of charging metals with helium were presented. Tritium was dissolved into vanadium and niobium specimens at elevated temperatures, allowed to decay to helium at room temperature, and then removed from the given specimen by hot vacuum extraction. Post-high-temperature test 3He concentrations up to 500 appm were achieved and were found to agree within ±7% with tritium decay concentration calculations. Substantial ductility decreases were found in niobium specimens tested at 1020°C and containing >130 appm helium. The ductility losses appeared to correlate with the appearance of helium on the grain boundaries. A niobium specimen containing 170 appm helium and subjected to an 1800°C anneal exhibited a substantial loss of load-carrying grain-boundary area due to grain-boundary helium bubble formation.
