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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
J. P. Trapp, M. Moro, Melle D. Garreton, M. Vanbenepe, P. Renaud
Nuclear Science and Engineering | Volume 106 | Number 1 | September 1990 | Pages 88-93
Technical Paper | doi.org/10.13182/NSE90-A23762
Articles are hosted by Taylor and Francis Online.
An outline of the detection systems for cladding failure in Superphénix and the dimensioning methodology of these systems are presented, followed by 1. mock-up used, its representativeness relative to the Superphénix hot plenum, and the measurements that were made 2. model for transposing the mock-up tests to the reactor 3. comparison between the calculations and the tests carried out on the reactor, showing validity of the methodology.