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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Zdeněk P. Bažant
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 256-260
Technical Paper | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31643
Articles are hosted by Taylor and Francis Online.
An attempt has been made to explain the advantages of the behavior of prestressed concrete reactor vessels in a simple, brief, and qualitative form. In contrast to the property of spontaneous propagation of brittle fracture in massive steel plates, the failure of one prestressing wire or tendon does not propagate into the adjacent wires or tendons. The pressure-deflection curve does not end by a sudden failure, but the decrease of slope on approach to failure is gradual and even after formation of through cracks the vessel would close if depressurized. The energy absorption capability in post-elastic deformation is much higher than that of a steel vessel which could fail by brittle fracture. A weak part is the top closure slab, but if it is designed sufficiently thick to assure that a separation of a conical segment does not create a hole through the slab, and if much higher safety factors are used than those for the barrel sections, a very favorable failure behavior is assured. Comparison of the behavior of concrete and steel vessels in accidental exposure to high temperature and the role of moisture in concrete deserve further investigation.