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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
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Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Dan Shen, Germina Ilas, Jeffrey J. Powers, Massimiliano Fratoni
Nuclear Science and Engineering | Volume 195 | Number 8 | August 2021 | Pages 825-837
Technical Paper | doi.org/10.1080/00295639.2021.1880850
Articles are hosted by Taylor and Francis Online.
The deployment of molten salt reactors requires validation of the computational tools used to support the licensing process. The Molten Salt Reactor Experiment (MSRE), built and operated in the 1960s, offers a unique inventory of experimental data for reactor physics benchmarks. The first benchmark based on the MSRE appeared in “The 2019 Edition of the IRPhEP [International Reactor Physics Experiment Evaluation Project] Handbook.” The benchmark refers to the first criticality experiment at zero power, stationary salt, and uniform temperature with 235U fuel. Simulations carried out for the developed benchmark model with the Monte Carlo code Serpent and ENDF/B-VII.1 cross-section library found that the calculated neutron multiplication is 1.02132 (±3 pcm) and that the combined bias of the model and experimental uncertainty is below 500 pcm. Such discrepancy between the experimental and calculated keff is not uncommon in benchmarks for graphite-moderated systems. The model created through this effort paves the way to additional benchmarks targeting reactor physics quantities of interest beyond multiplication factor.