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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
Grant awarded for advanced reactor workforce needs in southeast U.S.
North Carolina State University and the Electric Power Research Institute have been awarded a $500,000 grant by the NC Collaboratory for “An Assessment to Define Advanced Reactor Workforce Needs,” a project that aims to investigate job needs to help enable new nuclear development and deployment in North Carolina and surrounding areas.
R. B. Vilim
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 292-308
Technical Paper | doi.org/10.13182/NSE98-A2007
Articles are hosted by Taylor and Francis Online.
A model-based method is developed to predict probabilistic margins to safety limits for passively safe reactors where the same physical mechanisms that control reactor behavior at power also control off-normal response. Model parameter values are estimated using the maximum likelihood method from the plant response to perturbations of flow, temperature, and rod reactivity applied during normal operation. The resulting model can be used to predict plant response to upsets and provide a probabilistic measure of how closely safety limits would be approached. The method is applied to the Integral Fast Reactor.