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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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May 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
Alex Salazar, Massimiliano Fratoni, Joonhong Ahn (Univ of California, Berkeley), Fumio Hirano (JAEA/International Research Inst for Nuclear Decommissioning)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 600-607
The safety assessment of a geological repository for used nuclear fuel must ensure that future generations are shielded from radiation from fission products, in particular those released by re-criticality events. An investigation is required to understand whether or not criticality can actually be achieved. In fulfilling this end, this study assesses the uncertainty in the composition and total mass of precipitates forming in the far-field due to variation in transport parameters. The Latin Hypercube Sampling technique is employed to generate an accurate, random distribution of variables employed in the transport model and to assess the uncertainty of attaining a critical mass. The average characteristics of the damaged fuel from the Fukushima Daiichi reactor cores is used as the reference waste form. Results are compared to the minimum critical masses of previous studies to assess the criticality safety margin.